The 12th International Conference on Environmental ... - Events

FINAL PROGRAM
ICEM’09/
DECOM’09
<strong>The</strong> <strong>12th</strong> <strong>International</strong> <strong>Conference</strong>
on Environmental Remediation and
Radioactive Waste Management
JOINTLY ORGANIZED BY
Date: 11-15 October 2009
Liverpool Arena and Convention Center, UK
www.icemconf.com
by kind permission of Sellafield Ltd.
by kind permission of Sellafield Ltd.

WELCOME TO ICEM’09/DECOM’09
We welcome you to the Twelfth <strong>International</strong> <strong>Conference</strong> on Environmental Remediation and Radioactive Waste
Management (ICEM’09). It is a global information exchange, featuring engineering and scientific solutions to
environmental problems. More than 600 scientists, engineers, managers, project directors, business representatives,
equipment vendors and government officials from more than 30 countries are expected to attend the conference, held this
year in Liverpool, United Kingdom, at the Liverpool Arena and Convention Center (ACC).
<strong>The</strong> Nuclear Engineering and the Environmental Engineering Divisions of the American Society of Mechanical Engineers
(ASME) have joined forces with the Institution of Mechanical Engineers and the Nuclear Institute (NI) for ICEM’09 and
DECOM’09. <strong>The</strong> conference and exhibition offer a unique opportunity to foster cooperation and establish contacts with
participants from many countries. <strong>Conference</strong> participants will be able to speak directly with peers who are reporting new
research, initiating and managing environmental projects, establishing national and international regulations and applying
new methods and equipment. ICEM’09 is expected to feature 350 technical papers, research presentations and discussions
of field applications. A diverse group of international organizations will be exhibiting related technologies and services.
We have organized this Final Program so you can easily find additional details on the technical program and ways to
participate. Also included is a listing of Exhibitors, Sponsors and their services, and the technical abstracts. Please take a
look inside for more details. We are sure you will find something of interest. We hope that you have a successful meeting
and welcome to Liverpool!
<strong>Conference</strong> General Co-Chairs Honorary Co-Chairs
Kenneth Kok, URS Washington Division (USA) Dr. Ines Triay, Assistant Secretary-US DOE
Fred Sheil, Sellafield Ltd. (UK) EM Program (USA)
Hans Forström, Director of Nuclear Fuel Cycle
<strong>Conference</strong> Manager and Waste Technology IAEA (AUSTRIA)
Gary Benda, ICEM’09 <strong>Conference</strong> Manager (USA) Stephen Henwood, Chairman, Nuclear
Decommissioning Authority (UK)
During the conference, in case of emergency,
contact + 44 (0) 777 1797 783 or + 44 (0) 207 9731 258
<strong>The</strong>re will be a guest message board located at the IMechE stand (in the exhibition hall)
and at the registration desk (on the second floor).
We would like to thank the following companies for sponsoring
the following events at the ICEM’09 <strong>Conference</strong>.
~ Platinum Sponsors ~
BNS NUCLEAR SERVICES — Host of the Golf Simulator
URS CORPORATION — Host of the Monday Luncheon
~ Gold Sponsors ~
AMEC — Host of the Tuesday Luncheon
~ Silver Sponsors ~
CH2M HILL • ENERGYSOLUTIONS INTERNATIONAL GROUP
NATIONAL NUCLEAR LABORATORY (NNL) • NSG ENVIRONMENTAL
VT GROUP • NUVIA LTD. • WESTINGHOUSE
~ Bronze Sponsor ~
ASSYSTEM ENERGY & NUCLEAR • DEWDROPS • PACTEC
WE THANK OUR MEDIA SPONSORS FOR YOUR SUPPORT
Maney Publishing • Nuclear Engineering <strong>International</strong> • Nuclear Future Journal

Table of Contents
ICEM’09/DECOM’09 Corporate Sponsors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Inside Front Cover
Background, Location and Contact Information . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
Objectives and Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
Format and Venue . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
City of Liverpool . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
Hotel Pre-registration. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
Travel & Currency. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
Foreign Exchange and Traveler’s Checks/Cheques (Currency) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
Disclaimer . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
Insurance and Liability . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
ICEM’09/DECOM’09 Organizing Societies and Cooperating <strong>International</strong> Agencies . . . . . . . . . . . . . . . . . . . . . . . . . . 3
U.S. Societies. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
European Societies. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
Cooperating <strong>International</strong> Agencies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
Social Events and Guest Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
Social Events . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
Welcome Reception (Sunday) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
Exhibit Reception (Tuesday) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
<strong>Conference</strong> Banquet (Wednesday) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
Guest Tours “Welcome Reception” . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
Tours #1-5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
<strong>Conference</strong> Registration. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
On-Site Registration Hours . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
Speaker/Author/Co-Chair - Check-in . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
Technical Events . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
Participating Attendees . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
<strong>Conference</strong> Venue . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
Major Topics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
Plenary - Opening Session . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
Poster Sessions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
Special Panel Sessions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
<strong>Conference</strong> Proceedings on CD-ROM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
Daily Speaker/Session Co-Chair Briefing. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
Lunch Periods . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
AV Office / Speaker Ready Area. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
Coffee/Tea Breaks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
Technical Tours . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
Acronym List. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
MAPS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10-12
Liverpool Region Map. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10
Liverpool City Map . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11
Convention Center - All Three Levels Map . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
Convention Center - 2nd Floor Map . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
Condensed <strong>Conference</strong> Schedule . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13
Technical Program Session Schedule . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13
Poster Session Schedule . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13
ICEM’09 A/V Schedule and Loading of Revised PowerPoints . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13
Technical Program at a Glance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14-15
Technical Program Descriptions - Sessions 1-63 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16-31
Exhibition Hours and Exhibitor Floorplan . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32
Exhibitor Listing (Alphabetical & Numerical) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 33
Exhibitor Company Descriptions & Ads . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34-57
Technical Program Abstracts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .58-139
Pre-Registered Attendees by Country. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 140-143
Pre-Registered Attendees by Last Name . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 143-146
ICEM’09 Confernce Program Organisers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 147
Steering Committee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 147
Technical Program - Track Co-chairs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 147
Session Organisers. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 147
Schedule of Events . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 148
Convention Center Map. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Inside Back Cover
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2
Background, Location and
Contact Information
Objectives and Background
<strong>The</strong> Twelfth <strong>International</strong> <strong>Conference</strong> on
Environmental Remediation and Radioactive Waste
Management (ICEM) promotes a broad global
exchange of information on technologies, operations,
management approaches, economics, and public
policies in the critical areas of environmental
remediation and radioactive waste management. <strong>The</strong>
conference provides a unique opportunity to foster
cooperation among specialists from countries with
mature environmental management programs and those
from countries with emerging programs. Attendees will
include scientists, engineers, technology developers,
equipment suppliers, government officials, utility
representatives and owners of environmental problems.
ICEM’09 is the twelfth in a series of biennial
international conferences on environmental remediation
and radioactive waste management organized by
ASME. <strong>The</strong> first conference was held in Hong Kong in
1987, followed by Kyoto, Japan; Seoul, Korea; Prague,
Czech Republic; Berlin, Germany; Singapore; Nagoya,
Japan; Bruges, Belgium; Oxford, England; Glasgow,
Scotland, and Bruges, Belgium in 2007. <strong>The</strong> ICEM
conferences benefit from worldwide participation from
more than 30 countries.
Format and Venue
<strong>The</strong> ICEM’09/DECOM’09 technical program includes
concurrent technical sessions in five subject tracks:
1) Low/Intermediate-Level Waste Management
2) Spent Fuel, Fissile, Transuranic, High-Level
Waste Management
3) Facility Decontamination and Decommissioning
4) Environmental Remediation
5) Environmental Management / Public Involvement
<strong>The</strong> technical program consists of an opening plenary
session and several parallel program tracks with up to
eight concurrent sessions. <strong>The</strong> sessions include 25
minute oral presentations, panels, and poster displays
which are designed to enhance dialogue between
presenters and participants.
<strong>The</strong> ICEM’09/DECOM’09 Program is divided into 63
technical sessions conducted over three and a half days.
A listing of the specific sessions within each of the five
technical program tracks can be found in the “Technical
Program at a Glance” section. <strong>The</strong> full registration fee
includes entrance to all technical presentations, the
exhibit hall, the Sunday evening Welcome Reception,
the Tuesday evening Exhibitor Reception, all
refreshments during the conference breaks and lunch
for three days. <strong>The</strong> meeting material provided includes
the final program which includes the technical session
abstract book, and a complete CD-ROM containing all
approved papers that were presented, which will be
mailed after the conference.
City of Liverpool
Liverpool ACC is the flagship project in Liverpool’s
year as the 2008 European Capital of Culture and the
new jewel in Liverpool’s crown. From the world
famous ferry across the Mersey, to sports, culture and
world-class shopping, Liverpool has it all. Liverpool
has more buildings listed as being historically important
than any UK city other than London - in fact,
Liverpool’s waterfront area is a world heritage site,
putting it on a par with the Taj Mahal, the Great Wall of
China and Stonehenge. Just a few of Liverpool’s other
cultural highlights include: World Museum Liverpool,
the Tate Gallery - the largest gallery of modern &
contemporary art outside of London, the Maritime
Museum - which centers on Liverpool’s illustrious
history as a mercantile city, and the magnificent St
George’s Hall. Liverpool is home to the most successful
football team in England, Liverpool FC. Other sporting
attractions include horseracing at Haydock Park and
numerous golf courses. Not to mention <strong>The</strong> Beatles.
Those ‘four lads who shook the world’ were all
Scousers, and their imprint on their hometown is a
strong one. From the excellent Beatles Story Museum
to the Magical Mystery Tours that will show you places
like Penny Lane, Strawberry Field and the Cavern Club,
it is clear how proud Liverpool is of its most famous
sons.
Hotel – Pre-registration
ICEM has teamed with <strong>The</strong> Corporate Team to assist in
room accommodations. If you have made your hotel
arrangements through <strong>The</strong> Corporate Team and you
need to reach them for any reason. Contact: <strong>The</strong>
Corporate Team, Phone UK: 0845 604 4060, Phone
<strong>International</strong>: +44 (0) 20 7592 3050, Fax: +44 (0) 20
7828 6439, or Email: events@corporateteam.com;
www.corporateteam.com/events/8488FS. <strong>The</strong>
ICEM’09 Committee is not responsible for any
violations of any ordinances, and all other claims of
losses, costs, and damages arising from the attendee’s
occupancy at any of the local hotels.
Travel & Currency
Transportation by Air to Liverpool
Manchester <strong>International</strong> Airport provides direct access
to and from major European and North American cities
and is a 50-minute drive or 40 minutes by train ride
from Liverpool. Alternatively, the Liverpool John
Lennon Airport is nine miles southeast of the city
center. <strong>The</strong> Airline 500 bus services runs to the city
center at least every 30 minutes (~GBP £3, one-way)
and the new Liverpool South parkway train station is
nearby, with regular bus service to and from the airport.
A taxi to the city center takes around 20 minutes and
costs ~GBP £12. Both airports are served by many
international carriers.
Transportation by Coach to Liverpool
Many UK coach operators run services to the Liverpool
Bus Station. <strong>The</strong> S2 and S3 city center circular buses
run every 15 minutes and cost just GBP £1 per journey
(free if you have a daily or weekly ticket).
Transportation by Rail to Liverpool
<strong>The</strong> easiest way to get to Liverpool from within the UK
mainland or from Manchester Airport is by train. Trains
leave from the airport several times every hour. It is not
necessary to order tickets in advance. Lime Street is the
national railway network station in Liverpool, and there
is a National Express coach station too. <strong>The</strong> Mersey
travel network makes getting around the Liverpool
region by rail or bus easy, whatever your individual
needs. Visit www.merseytravel.gov.uk or call Traveline
on +44 0871-200-2233 to plan your journey. Off-peak
day tickets and weekly passes are available.

Transportation by Ferry to Liverpool
<strong>The</strong> Mersey Ferry runs regularly between Liverpool’s
Pier Head and Seacombe and Woodside in the Wirral.
At the same port, the new cruise liner facility sees many
ocean-going liners touring Liverpool.
Foreign Exchange and Traveler’s
Checks/Cheques (Currency)
<strong>The</strong> conference secretary on-site will accept only GBP
(no US$ or Traveler’s Checks) for payment of any
registration or optional ticket fees. Visa and MasterCard
are also accepted.
Disclaimer
Neither ASME, Institution of Mechanical Engineers nor
NI can accept any liability for death, injury, or any loss,
cost or expense suffered or incurred by any person if
such loss is caused or results from the act, default or
omission of any person other than an employee or agent
of ASME, Institution of Mechanical Engineers, or NI.
In particular, neither ASME, Institution of Mechanical
Engineers, nor NI can accept any liability for losses
arising from the provision or non-provision of services
provided by hotel companies or transport operators. Nor
can ASME, Institution of Mechanical Engineers, nor NI
accept liability for losses suffered by reason of war
including threat of war, riot and civil strife, terrorist
activity, natural disaster, weather, flood, drought,
technical, mechanical or electrical breakdown within
any premises visited by delegates and/or partners in
connection with the conference, industrial disputes,
governmental action, regulations or technical problems
which may affect the services provided in connection
with the conference. Neither ASME, Institution of
Mechanical Engineers, or NI is able to give any
warranty that a particular person will appear as a
speaker or panelist.
Insurance and Liability
All participants are encouraged to make their own
arrangements for health and travel insurance. Neither
ASME, Institution of Mechanical Engineers, NI nor
their agents, can be held responsible for any personal
injury, loss, damage, accident to private property or
additional expenses incurred because of delays or
changes in air, rail, sea, road or other services, strikes,
sickness, weather or any other cause.
ICEM’09/DECOM’09
Organizing Societies and
Cooperating <strong>International</strong> Agencies
U.S. Societies
<strong>The</strong> Nuclear Engineering Division and the
Environmental Engineering Division of ASME are the
primary organizing societies of the ICEM conference.
Since its inception in 1987, the original as well as
current objective has been to conduct international
conferences on key environmental management topics
in locations convenient to large numbers of technical
experts from emerging environmental programs. ASME
is committed to continue to provide this global
conference wherever the greatest need and interest are
shown.
ICEM’09 is also organized in cooperation with the U.S.
Department of Energy (US DOE), the U.S. Nuclear
Regulatory Commission (US NRC) and the U.S.
Environmental Protection Agency (US EPA) along with
several other major international technical societies and
governmental organizations. Each agency has had
significant involvement with the ICEM series. <strong>The</strong> US
DOE is responsible for managing the wastes and
cleaning the sites from the past U.S. government
nuclear operations, thus the US DOE staff has viewed
this conference series as an opportunity to identify new
technical solutions and to provide information on the
results of their programs to the international
community. Federal regulatory participants from both
the US EPA and US NRC have also been active in
program development and participation.
European Societies
<strong>The</strong> ICEM conferences have always been conducted
jointly with a major local technical society and other
co-societies in the host country. For ICEM’09, the
Institution of Mechanical Engineers and the Nuclear
Institute will again help in the organization as they did
at ICEM’03 and ICEM’05. In addition, the Nuclear
Decommissioning Authority (NDA) will continue
supporting the ICEM conferences by participating as a
major UK cooperating agency.
Cooperating <strong>International</strong> Agencies
Since the beginning, the ICEM meetings have been
held in cooperation with major international
organizations responsible for programs and research in
radioactive waste management and environmental
remediation fields. <strong>The</strong> <strong>International</strong> Atomic Energy
Agency (IAEA) has been assisting this conference in
several ways. <strong>The</strong>ir support has included assistance in
the technical program preparation, presentation of
technical papers and other agency information,
promotion of the conference to their member states, and
providing financial and technical assistance.
Social Events and Guest Program
Social Events
<strong>The</strong> conference registration fee includes lunch for three
days (Monday to Wednesday), the Sunday Welcome
Reception and the Tuesday Exhibitor Reception.
Tickets for the <strong>Conference</strong> Banquet on Wednesday are
optional and are charged at a nominal price. Please note
space is limited and tickets will be issued on a firstcome
first-served basis.
Welcome Reception
Sunday: 18:00-20:00 Room: Exhibition Hall 2A
All conference participants are invited to attend the
Welcome Reception in the Exhibit Hall at the ACC on
Sunday from 18:00 to 20:00. Attendance is included in
the conference registration fee. Guests are welcome to
purchase a ticket at GBP £15 (USD $27) plus VAT.
Delegate badges are required to gain entry and will be
available at the registration desk between 16:00 - 19:00.
Exhibit Reception
Tuesday: 18:00-19:30 Room: Exhibition Hall 2A
A complimentary reception for registrants will be held
from 18:00 to 19:30 in the Exhibit Hall. Please take this
opportunity to review, evaluate and test the current
products and services of the exhibiting companies.
Guests are welcome to purchase a ticket at GBP £15
(USD $27) plus VAT. Delegate/guests badges are
required to gain entry.
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<strong>Conference</strong> Banquet
Wednesday: 19:00 Off Site: Britannia Adelphi Hotel
<strong>The</strong> entertainment hallmark of the ICEM conference is
the traditional and culturally festive banquet, reflective
of the host country. This year’s ICEM 2009 banquet
will be held at the Britannia Adelphi Hotel which is as
much a part of Liverpool’s heritage as the River
Mersey. <strong>The</strong> evening will begin at 19:00 with a wine
and ale reception as guests visit with other members of
the international ICEM family. At 20:00, guests will
enter the banquet room where you will be transported
back to the ‘swinging sixties’ where a band called the
Beatles topped the record charts all over the world.
What will the rest of the evening hold... one can only
“Imagine”! <strong>The</strong> Britannia Adelphi Hotel also known as
just “Adelphi Hotel” is located about six minutes by car
from the convention center at Ranelagh Place.
Tel: +44 (0) 151 709 7200.
A coach transport between the ACC and Adelphi is
available for banquet attendees. However, you are most
welcome to make your own way there if you prefer.
Coaches will leave the ACC at 18:45 and return from
the Adelphi at 23:45.
<strong>The</strong> ICEM <strong>Conference</strong> Banquet is an optional extra, but
truly memorable. <strong>The</strong>re is a nominal cost to attend for
fully registered conference participants. For conference
guests, a tickets and badge will be required to gain
entrance.
Guest Tours “Welcome Reception”
Monday: 08:30 Room: 4B
ICEM will sponsor a “Guest Welcome Reception” on
Monday morning hosted by Dianne Benda. Ms. Benda
has hosted our guests programs in Oxford, Glasgow and
Bruges and will do so again this year.
This “Guest Welcome Reception” will review all of our
scheduled tour options (1 per day, Sunday-Thursday) as
well as having a native Liverpool representative that
will be available to answer any questions you may have
about fabulous opportunities in the city and surrounding
areas for shopping and sightseeing. While there will be
tourism information available throughout the event, we
encourage you to visit with the representative on
Monday to answer questions and assist you in planning
your week in Liverpool and its surrounding areas to
make the most of your visit to Liverpool.
Upon availibilty, last minute tickets can be purchased.
You must arrive at lease a half hour prior to the
scheduled departure time of that scheduled tour. Only
GBP £ funds will be accepted.
Tour #1 - Day Trip, Southport £45+VAT
Sunday, October 11, 2009
Departure: 10:00 Return: 17:00
Depart Location: ACC - Water Side Loading Area
All conference participants and guests are invited to
take part in this trip to a classic English seaside resort.
You will travel by coach to Southport, accompanied by
a tour guide, where you will find glorious sandy
beaches, panoramic seafront and a Victorian pier.
Southport’s famous pier is the oldest surviving iron pier
in the UK and the longest overland pier in the country.
Described as sophisticated, cosmopolitan and vibrant,
Southport is the perfect place to enjoy a relaxing
daytrip. <strong>The</strong>re will be a guided tour around Southport
followed by free time to enjoy Southport’s Lord Street,
famous for its shopping. <strong>The</strong> leafy boulevard, with its
glass-canopied shops and stunning Wayfarers Arcade,
make it one of the Northwest’s leading shopping
destinations. <strong>The</strong> coach will pick up and drop off at the
ACC, Liverpool (returning in time to attend the Sunday
Welcome Reception).
Tour #2 - Liverpool City Tour £8+VAT
Monday, October 12, 2009
Departure: 10:00 Return: On your Own
Depart Location: Gowers Street
After meeting with the other guests for the welcome
orientation with coffee/tea and cookies, we will begin
our tour of the city with an open top Hop-On- Hop Off
guided tour bus. This is the best and easiest way to see
the city with 12 stops and narrations of the city sights
such as Albert Dock, <strong>The</strong> Cavern, Chinatown, the
cathedrals and other city sights. After the round trip tour
concludes, you may continue on the bus choosing
selected spots for shopping or lunch to visit on your
own or in small groups. Your bus ticket will continue to
provide you with transportation throughout the city for
the rest of the day (on this route only). <strong>The</strong> bus stops
near the Liverpool ACC for easy boarding and transport
throughout Liverpool.
Tour #3: - Port Sunlight and Chester £38+VAT
Tuesday, October 13, 2009
Departure:09:00 Return: 16:30
Depart Location: ACC - Water Side Loading Area
A visit to the unique village of Port Sunlight built by
William Lever for his factory workers then visit the
Lady Lever Art Gallery where we will enjoy tea and
biscuits. <strong>The</strong>n on to the Roman city of Chester, 20 miles
away, for a guided walk, lunch at the Chester Cathedral
Rectory or surrounding eateries, and then free time for
shopping and tea in this historic and quaint city. Lunch
or refreshments are not included.
Tour #4: Beatles Magical Mystery Tour £58+VAT
Wednesday, October 14, 2009
Departure: 10:00 Return: 15:00
Depart Location: ACC - Water Side Loading Area
Your trip to Liverpool would not be complete without a
visit to <strong>The</strong> Beatles Story Museum followed by the two
hour Magical Mystery coach tour. This day will
introduce you to the lives of the Beatles visiting their
homes, schools and places that inspired some of their
most memorable songs ending at the legendary Cavern
Club. This full day experience will leave you immersed
in Beatle mania and ready for ICEM’s legendary
Cultural Banquet. Lunch or refreshments are not
included.
Tour #5: Liverpool Anglican £46+VAT
Cathedral & Speke Hall
Thursday, October 15, 2009
Departure: 09:00 Return: 17:00
Depart Location: ACC - Water Side Loading Area
A guided visit through the country’s largest cathedral,
followed by a coach tour to the superb Tudor House,
Speke Hall. This rambling, atmospheric house spans the
centuries - with a fine Great Hall and priest hole from
the 16th century and an Oak Parlour and smaller cozy
rooms from the Victorian era. Jacobean plasterwork and
intricately carved furniture complete the picture. <strong>The</strong>
fully equipped Victorian kitchen and servant’s hall give
a fascinating ‘below stairs’ experience. Lunch and
refreshments are not included.

<strong>Conference</strong> Registration
On-Site Registration Hours
It is strongly recommended that the conference
participants register on Sunday, October 11, to avoid the
rush before the opening session on Monday morning,
October 12. Badges are required for the Sunday
Reception. <strong>The</strong> registration desk will be located in the
ACC on the 2nd floor foyer area, during the following
hours:
Sunday, October 11, 2009 16:00 to 19:00
Monday, October 12, 2009 07:15 to 18:00
Tuesday, October 13, 2009 07:15 to 18:00
Wednesday, October 14, 2009 07:15 to 18:00
Thursday, October 15, 2009 07:15 to 10:00
Speaker/Author/Co-Chair - Check-in
Upon your arrival and after you check-in at the
registration counter, please proceed to the
Speaker/Author check-in desk located on the second
floor. Here you will confirm your attendance,
presentation times, review your submitted documents
and hand in any last minute paperwork for the
conference.
Hours
Sunday, October 11, 2009 16:00 to 19:00
Monday, October 12, 2009 07:15 to 18:00
Tuesday, October 13, 2009 07:15 to 18:00
Wednesday, October 14, 2009 07:15 to 18:00
Thursday, October 15, 2009 07:15 to 13:00
Please be sure that you also attend the Speaker/Session
Co-Chair Briefing (continental breakfast) on the day of
your presentation in room 11B at the ACC. Full details
regarding your attendance are on page 7.
Technical Events
Participating Attendees
Over 300 abstracts have been accepted from more than
30 countries, from Western, Central and Eastern Europe,
the Far and Middle East, and from North and South
America. This strong technical program is expected to
draw more than 600 scientists, engineers, managers,
project directors, utility and other business
representatives, equipment vendors and government
officials from around the world. <strong>The</strong> traditionally strong
participation from countries with mature environmental
programs will be supplemented by a contingent of
attendees from Central and Eastern Europe, as well as
key representatives from other countries from around
the world with emerging programs. In the past, the
ICEM meetings have allowed participants to exchange
technical information, discover solutions to problems
and make valuable business contacts or even arrange
business agreements.
<strong>Conference</strong> Venue
<strong>The</strong> 2009 conference will be held at the Liverpool Arena
and Convention Center (ACC) situated in the beautiful
location of the Kings Dock on the River Mersey. It
consists of the Echo Arena and the BT Convention
Center. <strong>The</strong> ACC offers visitors a unique experience in
one of the UK’s most vibrant cities. Host to the opening
ceremony of the Capital of Culture Year in January
2008, Echo Arena Liverpool is the center of
entertainment for concert goers and sports enthusiasts
across the North West and North Wales. <strong>The</strong> Arena and
Convention Center Liverpool is located at Monarchs
Quay, Liverpool, L3 4FP. Most accommodations are
within a 10-15 minute walk of the conference center.
Major Topics
<strong>The</strong> ICEM’09 Technical Program is divided into 63
technical sessions conducted over three and one-half
days. A listing of the specific sessions within each of
the six technical programs can be found in the
“Program at a Glance” Section.
Plenary - Opening Session
Monday: 09:00 Room: Hall 1A
<strong>The</strong> Opening Session will take place at the Liverpool
Arena and Convention Center (ACC) on Monday
morning at 09:00 with the keynote presentations setting
the theme for this year’s conference. Coffee will be
served in the exhibit hall from 07:30 until the program
begins at 09:00. Our current confirmed speakers are
listed below:
PLENARY SPEAKERS & HONORARY
CO-CHAIR’S:
Dr. Inés Triay: Assistant Secretary for Environmental
Management-DOE (USA)
Hans Forström: Director, Nuclear Fuel Cycle and
Waste Technology-IAEA (AUSTRIA)
Stephen Henwood: Chairman, Nuclear
Decommissioning Authority (UK)
Bill Poulson: Managing Director, Sellafield Ltd. (UK)
Poster Sessions
<strong>The</strong> conference technical program will contain five
major Poster Sessions on Monday, Tuesday and
Wednesday arranged from the five Technical Tracks.
<strong>The</strong> leading objective for the poster sessions is to
provide a forum for experts in the field and interested
attendees to gather for a half day in the ACC where
they can move around freely and engage in discussions,
which would normally not be possible during the oral
sessions.
Special Panel Sessions
PANEL: Environmental Cleanup Worldwide -
Challenges and Opportunities – Session 2A
Monday: 13:45 Room: 3A
This panel will provide a global perspective on the
current status of environmental management in the
world...
Panelists include: Marc Butez, CEA (FRANCE);
Hiroyuki Umeki, JAEA (JAPAN); Myung Jae Song,
Doosan (KOREA); Adrian Simper, NDA (UK); and
Samit Bhattacharyya, SRNL (USA).
PANEL: Will the Lack of Geological Repositories
Slow the Nuclear Renaissance? – Session 2B
Monday: 16:15 Room: 3A
<strong>The</strong> continued growth in interest in expanding nuclear
power programand the continuing challenge of implementing
geological disposal are strongly related issues.
New nuclear plants may be more acceptable if “the
waste problem” is seen to be solved – and thus more
effort may be devoted to this task. On the other hand,
the urgent need for more, CO2 free electricity may
tempt decision makers to downplay the back-end
issues. In either case, there may be direct impacts on
national disposal programand also on the support given
to multinational disposal initiatives that may provide
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small and new nuclear programwith earlier, more
affordable, access to safe and secure repositories.
Panellists include: Professor W.E. (Bill) Lee, Imperial
College (UK); Hiroyuki Umeki, JAEA (JAPAN);
Ewoud Verhoef, COVRA (NETHERLANDS); and
Charles McCombie, Arius Association (UK).
Hot Topics and Emerging Issues in
D&D – Session 3
Monday: 13:45 Room: 3B
This panel will focus on current hot topics and emerging
issues in the decommissioning area worldwide. <strong>The</strong>
topics being considered include critical issues facing
D&D, privatization, supply chain issues, disposal
issues, cost-effectiveness, loss and retention of skills,
and international cooperation and networking.
Panelists include: Dr. Jas Devgun, Sargent & Lundy
LLC, (USA); Dr. Michele Laraia, IAEA (AUSTRIA);
Russ Mellor, Sellafield (UK); Dr. Charles Miller, US
Nuclear Regulatory Commission (USA); Mr. Richard
Mrowicki, NDA (UK); David Boath, AMEC (UK);
and Brad Smith, CH2M Hill (USA).
PANEL: YGN Roundtable “An Audience With...” –
Session 11A
Monday: 16:15 Room: 13
This round table discussion was developed due to the
fact that YGN members/panel in the UK don’t know
where to turn for career advice and feel that there is a
glass ceiling for progression dependent on age which
we want to investigate.
<strong>The</strong> session will be led by Russ Mellor, Decommissioning
Director at Sellafield Ltd and Miranda
Kirschel, Business Development Director at CH2M
HILL, <strong>International</strong> Nuclear Services. Both have had
varied and interesting career paths and are happy to
share their experiences with younger members of
industry in a relaxed round table environment with
plenty of time for questions and discussion. <strong>The</strong> session
is aimed at the encouragement for career development
of younger members of industry and to investigate
if there is a glass ceiling stopping career progression
in UK or elsewhere in the world.
YGN GENERAL MEETING – Session 11B
Monday: After Session 11A Room: 13
A general YGN Meeting will be conducted to canvass
views of the younger members of the industry,
exchange knowledge across companies, and grow the
YGN network through the conference attendees. This
meeting will be used to share best practices, and
develop new ideas to progress the aims and objectives
of the YGN in the future.
Agenda: 1) Introductions; 2) Explanation of YGN Aims
and Objectives; 3) Discussion on Output of YGN
Questionnaire; 4) Sharing of <strong>International</strong> YGN Activities
and Events; 5) Personal Development and Career
Progression; 6) Education and Training Initiatives; 7)
Communications across the YGN Network; 8) External
Communications to wider industry and 9) Future Plans
and New Initiatives.
PANEL: Emerging Issues in the Management for
L/ILW – Session 13
Monday: 08:30 Room: 3B
This panel will focus on strategies for the management
of all low and intermediate level waste (L/ILW). Based
on experience in different national programs, it will
discuss various options and their merits for managing
L/ILW. It will consider the definition of different categories
of L/ILW and their potential routes for disposal
including waste of very low activity, often arising in
high volumes as contaminated land or from decommissioning.
Panelists include: Mr. Phil Davies, NDA, Head of
National Waste Mgmt. Strategy (UK); Mr. Hans
Forström, Director, Nuclear Fuel Cycle & Waste Technology
- IAEA, (AUSTRIA); Dr. S. D. Misra, Director
of Nuclear Recycle Group, BARC, (INDIA); Mr.
Michel Dutzer, Director Industrielle, ANDRA
(FRANCE); and Mr. David Bennett, Strategic Policy
Manager, Environmental Agency of England and Wales
(UK).
PANEL: <strong>International</strong> Decommissioning Network –
Session 14
Monday: 08:30 Room: 12
This panel will focus on IAEA’s <strong>International</strong> Decommissioning
Network (IDN). In this session IDNinvolved
organizations will be invited to report on their
experience in cooperating with the IAEA in the field of
decommissioning. <strong>The</strong> panel will be introduced by an
overview of progress achieved and plans developed
under the IDN. Since the IDN is intended to function
as a loose “Network of Networks”, other presentations
in this session should include work involving bilateral /
multinational agreements carried out by non-IAEA
organizations which form complementary “Networks”.
Active discussion can be expected to ensure dissemination
of information about and support for the IDN concept
by organizations not involved yet.
Panelists include: Staffan Linsdkog, SKI (Sweden);
Sean Bushart, EPRI, (USA); Leopold Weil, Federal
Office for Radiation Protection (BfS), (Germany);
Maria Lindberg, Studsvik UK Ltd, (UK); Doug Metcalfe,
Natural Resources Canada, (Canada); and
Michele Laraia, <strong>International</strong> Atomic Energy Agency
(IAEA), (Austria).
PANEL: Global Partnering in <strong>International</strong> Waste
and Cleanup Programs – Session 20
Monday: 10:45 Room: 11B
This panel will provide a global perspective on the
status of the clean-up of nuclear legacy sites in the
North West and Far East Russia and lessons learned by
key participants of the Global Partnership Program. <strong>The</strong>
speakers will discuss best practice in international
cooperation, meeting regulatory requirements and
approaches to ensure safe management of spent nuclear
fuel and radioactive waste. Speakers in this session will
discuss their Global Partnership activities, and explore
opportunities for future international collaboration.
Panelists include: Michael Washer, Department of
Foreign Affairs and <strong>International</strong> Trade (Canada);
Aleksey Maltzev, FSUE Zvyozdochka (Russia)
Konstantin Kulikov, NIPTB Onega (Russia); Sergey
Kazakov, Director of the Federal Nuclear Safety
Centre (Russia); and Lucien Pillette-Cousin, AREVA
(France)
PANEL: Current IAEA Activities in
Predisposal Management of L/IL Radioactive
Waste – Session 23
Tuesday: 13:45 Room: 3A
This panel will focus on Waste Technology Section
(WTS) of the <strong>International</strong> Atomic Energy Agency
(IAEA) which has a dedicated program focused on
waste predisposal activities. <strong>The</strong> objective of this program
is to strengthen the capability of Member States
to properly and safely process and store radioactive
waste. A range of activities are included in this pro-

gram to provide guidance on selection and program of
waste management strategies, to provide information
and guidance on best practices and technologies for
waste minimization, pre-treatment, treatment, conditioning,
packaging, transportation and storage, to support
research and development on new pre-disposal
technologies, etc. This panel will provide a forum for
the exchange of scientific and technical information
and guidance on pre-disposal radioactive waste management
with focus on current activities. <strong>The</strong> following
topics will be discussed by our panel with an opportunity
for interaction with the audience.
Panelists and Topics include: Dr. Antonio Morales
Leon - Approach to Development of Waste Acceptance
Criteria for all Individual Waste Management Steps:
Pre-treatment to Disposal; Zoran Drace - Economics
of Radioactive Waste Management - Cost Calculations
and Approach to Costing of Future Obligations (Liability
Assessment); Dr. Antonio Morales Leon - Standardized
Methodology for Waste Management Assessments
- An Optimized Approach to Establish Current
and Future needs and to Select Adequate Technical
Options; Dr. Sustanta Kumar - Modular and Mobile
Waste Processing Facilities; Zoran Drace - Long-term
Storage for L&IL and HL Waste - Technical Considerations;
Zoran Drace/Dr. Antonio Morales Leon -
Mixed Waste Processing/Storage and Disposal; and Dr.
Antonio Morales Leon - IAEA Network for Radioactive
Waste Characterization - Processing/Storage/Disposal.
PANEL: Young Generation Network (YGN) –
Session 44
Wednesday: 10:45 Room: 11B
This panel will focus on Young Generation Network
and Professional Development. <strong>The</strong> panelists and topics
will include Carl Dawson (NDA Graduate Program
Manager) and Craig Morrow (NDA Graduate) on the
creation and experiences of the Nuclear Decommissioning
Authority Graduate Scheme; Corhyn Parr
(UK YGN Vice Chair) presenting the results of a survey
of UK YGN members on attitudes and opinions of
the UK Nuclear Industry and Miguel Millan (Spanish
YGN) on the Development of the Spanish YGN.
PANEL: UK NDA and Tier 1 Funding, Contracting,
Subcontracting Selection and Arrangements –
Session 46
Wednesday 13:45 Room: 3A
This workshop will summarize and provide a status
report on funding, contracting and the competition program
for the NDA sites. <strong>The</strong> focus will be to discuss
openly with the audience’s experience, ideas and new
lessons that are applicable to the UK.
Panelists include: Mike Hawe, Commercial Director,
Magnox North; Keith Case, Commercial Director, Sellafield;
David Savage, Program Manager, Shared Services
Alliance; Ron Gorham, Head of Supply Chain
Development, NDA; and Keith Gibson, Low Level
Waste Repository.
PANEL: UMREG Panel/Roundtable – Session 47
Wednesday 13:45 Room: 3B
This panel with meeting roundtable will focus on uranium
mine and mill remediation issues as contemplated
by the international IAEA, Uranium Mining Remediation
Exchange Group (UMREG). UMREG constituted
itself during the ICEM’95 Berlin Meeting as an informal
network group for multilateral exchange on issues
related to uranium mine and mill remediation. <strong>The</strong>
USDOE UMTRA-Group and the German BMWi-WIS-
MUT Group started the exchange in 1993 on specific
topics related to major projects UMTRA Title I and
WISMUT. Since then, several meetings were held in
conjunction with international conferences focusing on
environmental remediation. Also, the Group has grown
into an international network including representatives
of regulating, permitting and supervising institutions,
operating and consulting companies, and research
organizations.
Panelists include: Alex Jakubick, UMREG (AUSR-
TIA); Jody Waugh, S. M. Stoller Corp., US DOE Contractor
(USA); Michael Paul, Wismut (GERMANY);
Marat Kaftaranov, Uranlikvidrudnik (KAZA-
KHSTAN); Peter Stegnar, NATO Central Asian Program
(SLOVENIA); Steve Brown, SENES Consultants
Ltd. (USA); Földig Gabor, MECSEK-ÖKO
(HUNGARY); Peter Waggitt, IAEA (AUSTRALIA)
and Esther Harlander, EBRD (UK)
PANEL: Future Direction in Knowledge
Management – Session 53
Wednesday 10:45 Room: 12
This panel will consider the initiative instigated by
JAEA in the context of the common requirement to
efficiently and rigorously manage increasing large and
complex fluxes of information produced in all
geological disposal programs. Emphasis will be on
distinguishing between program-specific constraints
and more generic areas, which could be a focus for
future collaborative projects.
Panelists include: P. Marjatta Palmu, Posiva Oy,
(FINDLAND); Richard Shaw, British Geological Survey
(BGS), (UK); Stuart Hunt, Nuclear Decommissioning
Authority, (UK); and Hiroyuki Umeki, Japan
Atomic Energy Agency, (JAPAN).
<strong>Conference</strong> Proceedings on CD-ROM
Each conference registrant will receive the conference
proceedings on a CD-ROM mailed approximately three
months after the conference. Additional proceedings
may be ordered at an additional charge, by contacting:
ASME Order Department, 22 Law Drive, P.O. Box
2300, Fairfield, NJ 07007-2300, U.S.A., Telephone
1-800-THE-ASME.
Daily Speaker/Session Co-Chair Briefing
A morning briefing will be provided to all Speakers,
Panelists, and Session Co-Chairs on the day of their
session. <strong>The</strong> briefing will include coffee, tea, and
biscuits and will be served at the conference center.
Most hotels have breakfast included in the cost of the
room. <strong>The</strong> speaker’s briefing will give you the time for
final arrangements before your session. <strong>The</strong> attendance
at the briefing will provide an opportunity for the
Session Co-Chairs to meet with the speakers, and for all
to discuss the topics they will be addressing. It is
essential that all Panel and Oral Speakers/Co-Chairs
attend the briefing.
Monday, October 12, 2009 08:00 to 08:30
Room/Location: 11B
Tuesday, October 13, 2009 07:30 to 08:00
Room/Location: 11B
Wednesday, October 14, 2009 07:30 to 08:00
Room/Location: 11B
Thursday, October 15, 2009 07:30 to 08:00
Room/Location: 11B
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Lunch Periods
Lunch will be served in the Exhibit Hall. Lunches served on
Monday, Tuesday and Wednesday will mainly consist of hot
fork buffet food that can be easily consumed while visiting
the exhibits and posters. Luncheon hours are from 12:30 -
13:40. Paid full week registration includes the luncheon price
for all three days. If you prefer, there are also several local
restaurants near the conference center. A listing of local
restaurants for eating and drinking’ a will be given to
delegates upon arrival Additional information can be found
on their website at: www.accliverpool.com/liverpool.
AV Office / Speaker Ready Area
Room: 7 — Monday-Wednesday
<strong>The</strong> AV Office / Speaker Ready area will be available for
speakers to load and review their PowerPoint slides. This
area will be open from Monday to Wednesday from 07:15 -
17:00 on the 2nd floor room 7 at the <strong>Conference</strong> Center.
Please refer to the AV schedule on page ??.
Acronym List
ACC Arena and Convention Centre
AEA Atomic Energy Agency
ALARA As Low As Reasonably
Achievable
ASME American Society of
Mechanical Engineers
BWR Boiling Water Reactor
CEA Commissariat a l’Energie
Atomique
CERCLA Comprehensive Environmental
Response, Compensation and
Liability Act
CH-TRU Contact Handled- Transuranic
Waste
DAW Dry Activated Waste
DNFSB Defense Nuclear Facilities
Safety Board
DOE Department of Energy
EIS Environmental Impact
Statement
EM Environmental Management
EPA Environmental Protection
Agency
EPRI Electric Power Research
Institute
ER Environmental Remediation
FUSRAP Formerly Utilized Sites
Remedial Action Program
HEPA High Efficiency Particulate Air
HEU Highly Enriched Uranium
HLW High Level Waste
IAEA <strong>International</strong> Atomic Energy
Agency
IDN <strong>International</strong> Decommissioning
Network
ILW Intermediate Level Waste
IPSN Institut de Protection et de
SureteNucleaire
ISM Integrated Safety Management
JAERI Japan Atomic Energy Research
Institute
KAERI Korea Atomic Energy Research
Institute
LEU Low Enriched Uranium
LILW Low- intermediate Level Waste
LLW Low Level Waste
LSA Low Specific Activity
M&I Management & Integration
M&O Management & Operation
MOX Mixed Uranium-Plutonium
Oxide
MW Mixed Waste
N-DA Non-Detectable Activity
NDA Nuclear Decommissioning
Authority
NEA Nuclear Energy Agency
NED Nuclear Engineering Division
NEI Nuclear Energy Institute
NEPA National Environmental Policy
Act
NI Nuclear Institute
NNSA National Nuclear Security
Administration
NORM Natural Occurring Radioactive
Material
NPO Nuclear Power Operations
NPP Nuclear Power Plant
NWPA Nuclear Waste Policy Act
Coffee/Tea Breaks
Complimentary coffee and tea will be served for all
meeting participants in the Exhibit Hall during the
morning and the afternoon breaks each day of the
conference.
Technical Tours
Four technical tours are planned to see the UK
radioactive waste management programs first hand.
<strong>The</strong>se tours will take place immediately after the
conference on Thursday and Friday. <strong>The</strong>se tours are
full, however a cancellation could have occurred.
Please check-in at our registration desk to confirm your
attendance if you registered for a tour. If you are
interested as a replacement for a cancellation, please
also contact us for the available options.
Tour 1A - Sellafield
(Sponsored by Nuclear Management Partnership)
Tour 1B - UK Low Level Waste Repository
Tour 2 - Springfield Fuel Fabrication Plant
Tour 3 - Trawsfynydd
OECD Organization for Economic
Cooperation & Development
PRA Probabilistic Risk Analysis
PWR Pressurized Water Reactor
R&D Research & Development
RCRA Resource Conservation and
Recovery Act
RH-TRU Remote Handled- Transuranic
Waste
ROC Republic of China
RPV Reactor Pressure Vessel
RW Rade Waste
SNF Spent Nuclear Fuel|
SRNL Savannah River National
Laboratory
SRW Solid Radioactive Waste
TENORM Technologically Enhanced
Naturally Occurring Radioactive
Material
TRU Transuranic
TRUPACT Transuranic Package
Transporter
USACE United States Army Corps of
Engineers
USDOD US Department of Defense
USDOE US Department of Energy
USNRC US Nuclear Regulatory
Commission
WAC Waste Acceptance Criteria
WIPP Waste Isolation Pilot Plant
WM Waste Management
WNA World Nuclear Association

Notes
9

10
Liverpool Region

Liverpool City Center Map
Bus
Loading
11

12
Convention Center — Cross Section of All Three Levels
Escalator to
the 1st floor
1. Convention Center Entrance
1st Floor
4. Exhibition Hall Entrance
Basement Level
Convention Center — 2nd Floor
Entrance at 1st Floor
2. Registration and Technical Meeting Ro oms 3. Exhibitor Loading Bay
(Riverside Terrace) — 2nd Floor
Basement Level
5. River Mersey 6. Tour Bus Loading Area
Entrance at 1st Floor
Registration Area
Meeting Room Locations
Meeting Room Locations
This is a view of the 2nd Level
of the <strong>Conference</strong> Center
Room 1
Plenary
Session
Guest, Technical Tours
and Wednesday Evening
Banquet buses will
load/unload from this
area of the ACC.
River Mersey Side

Condensed <strong>Conference</strong> Schedule
ICEM’09
Tracks
Technical Program Session Schedule
Approximate Presentation Times
Morning Presentation Start Time
Session Start 8:30
Paper 1 8:35
Paper 2 9:00
Paper 3 9:25
Paper 4 9:50
Break 10:15- 10:40
Session Start 10:45
Paper 5 10:50
Paper 6 11:15
Paper 7 11:40
Paper 8 12:05
Session Ends 12:30
Lunch 12:30-13:40
<strong>The</strong> above approximate presentation times are provided so you can tentatively arrange your schedule. We rely on the Session Co-Chairs to
manage the presentations to this schedule so that you can move between sessions and attend the presentations you desire. We recognize
however that due to cancellations or other unplanned events, the order time may be changed at the conference. <strong>The</strong> session posters outside
each speaking room are intended to show the cancelled papers and any changed times. We also encourage the Session Co-Chairs to
manage the session time in the best interest for the majority of the attendees and request that they mark any changes on the posters before
the session starts. We offer our regrets if you missed a presentation due to these changes.
Poster Session Schedule
ICEM’09 A/V Schedule and Loading of Revised PowerPoints
Afternoon Presentation Start Time
Session Start 13:45
Paper 1 13:50
Paper 2 14:15
Paper 3 14:40
Paper 4 15:05
Break 15:30 -16:10
Session Start 16:15
Paper 5 16:20
Paper 6 16:15
Paper 7 17:10
Paper 8 17:35
Session Ends 18:00
Poster Times Set-Up Poster Displayed Poster Presenter at Booth Tear Down
Session 12
Session 22
Session 34
Session 45
Session 56
Mon. pm - Mon. pm Tues. am - Tues. pm Wed. am - Wed. pm Thurs. am
Low Level /
Intermediate Level WM
High Level Waste /
Spent Nuclear Fuel WM
Decontamination
& Decommissioning
Environmental
Remediation
Environmental Mgmt /
Crosscutting Issues
Posters
#1
L
U
N
C
H
12:30 – 13:30
08:00 – 08:30
12:30 – 13:30
08:00 – 08:30
12:30 – 13:30
#4 #13
#5 #6 #15
#2A #2B #16
#17
#3 #18
#14
#7 #8
#10 #11 #19 #20
#9
#21
#12 #22
13:30 – 17:45
08:30 – 12:45
13:30 – 17:45
08:30 – 12:45
13:30 – 17:45
#23
#27
#28
#29 #30
#25 #26
#24
#31
#32 #33
#38
#39 #40
#41
#36
#37
#42 / #43
#44
#45
15:30 – 16:10 17:15 - 17:45
10:15 – 10:40 12:15 – 12:45
15:30 – 16:10 17:15 - 17:45
10:15 – 10:40 12:15 – 12:45
15:30 – 16:10 17:15 - 17:45
#48
#59
#49 #50 #60
#51 #61
#52 #53
#54 #57
#55 #58
#47 #62
17:45 – 18:00
12:45 – 13:00
17:45 – 18:00
12:45 – 13:00
17:45 – 18:00
Please Note: If your poster presentation is not removed by the above listed times, your presentation will be removed by the
association and held at the speaker check-in desk until the end of the conference (Thursday, October 15, 2009 @12:30).
If you do not pick up your presentation before the conference ends, your presentation will be discarded).
L
U
N
C
H
Monday 7:15 - 9:30 Reserved for Monday Morning Plenary Loading/Transfer/Set-up Session 1
Monday 9:30 - 12:30 Reserved for Loading Monday Afternoon Sessions 2-12
Monday 12:30 - 14:00 Reserved for Monday Afternoon Transfer/Set-up Sessions 2-12
Monday 14:00 - 17:00 Loading Powerpoints — All Sessions 13-63
Tuesday 7:15 - 9:00 Reserved for Tuesday Morning Transfer/Set-up Sessions 13-22
Tuesday 9:00 - 12:30 Reserved for Loading Tuesday Afternoon Sessions 23-34
Tuesday 12:30 - 14:00 Reserved for Monday Afternoon Transfer/Set-up Sessions 23-34
Tuesday 14:00 - 17:00 Loading Powerpoints — All Sessions 35-63
Wednesday 7:15 - 9:00 Reserved for Wednesday Morning Transfer/Set-up Sessions 35-45
Wednesday 9:00 - 12:30 Reserved for Loading Wednesday Afternoon Sessions 46-56
Monday 12:30 - 14:00 Reserved for Wednesday Afternoon Transfer/Set-up Sessions 46-56
Wednesday 14:00 - 17:00 Loading Powerpoints — All Sessions 57-63
Thursday 7:15 - 9:00 Thursday Morning Transfer/Set-up Sessions 57-63
#34
L
U
N
C
H
#46
#56
#63
13

SESSION #
14
Technical Program at a Glance
MONDAY AM - OCTOBER 12, 2009
1 Opening Session ALL X Room 1 09:00
MONDAY PM - OCTOBER 12, 2009
2A Panel: Environmental Cleanup Worldwide - Challenges and Opportunities X X Room 3A 13:45
2B Panel: Will the Lack of Geological Repositories Slow the Nuclear Renaissance X Room 3A 16:15
3 Hot Topics and Emerging Issues In D&D X Room 3B 13:45
4 National Programs For L/ILW X Room 12 13:45
5 LLW Characterization, Treatment & Packaging Developments - Part 1 of 2 X Room 4B 13:45
6 LLW Characterization, Treatment & Packaging Developments - Part 2 of 2 X Room 4B 16:15
7 National and <strong>International</strong> ER Programs X Room 11B 13:45
8 Experiences In ER Clean-Up Actions X Room 11B 16:15
9 National, Multi-National and <strong>International</strong> Programs X Room 11C 13:45
10 EM Life-Cycle Economics and Cost-Benefit Analysis X Room 13 13:45
11A Panel: YGN Roundtable “An Audience With”... X Room 13 16:15
11B General YGN Meeting (Directly after Session 11A) X Room 13
12 Poster Session: Spent Fuel, Fissile, TRU and HLW Management X 2nd Floor 13:30
TUESDAY AM - OCTOBER 13, 2009
13 Panel: Emerging Issues in the Management For L/ILW X Room 3B 08:30
14 Panel: <strong>International</strong> Decommissioning Network X Room 12 08:30
15 Disposal Site and Waste Form Characterization and Performance Assessment X Room 4B 08:30
16 National and <strong>International</strong> Programs For Spent Fuel, Fissile, TRU, and HLW Management X Room 3A 08:30
17 HLW Characterization / Recent Advances in HLW Treatment Systems X Room 13 08:30
18 D&D of Power Reactors and Research Reactors X Room 11C 08:30
19 Global Partnering in <strong>International</strong> Clean-Up Programs X Room 14 08:30
20 Panel: Global Partnering in <strong>International</strong> Waste and Cleanup Programs X Room 11B 10:45
21 Environmental Management Health and Safety Issues X Room 14 10:45
22 Poster Session - Facility Decontamination and Decommissioning X 2nd Floor 08:30
TUESDAY PM - OCTOBER 13, 2009
SESSION TITLES
23 Panel: Current IAEA Activities in Predisposal Management of L/ILRadioactive Waste X Room 3A 13:45
24 National and <strong>International</strong> D&D Programs X Room 3B 13:45
25 Treatment, Management and Recycle of D&D Materials X Room 4B 13:45
26 D&D Update and Management Issues X Room 4B 16:15
27 Waste Minimization, Avoidance and Recycling X Room 11B 13:45
28 Repository Programs: Site Selection & Characterization, URL, Eng. & Geological Barriers X Room 11C 13:45
29 Modeling Approaches for HLW, SNF, and TRU Waste Disposition X Room 12 13:45
30 Spent Fuel, HLW, and TRU Waste Management - Crosscutting Issues X Room 12 16:15
31 ER Site Characterization and Monitoring - Part 1 of 2 X Room 13 13:45
32 Local Participation and Decision-Making Processes, Behavior and Politics X Room 14 13:45
LLW
HWL
D&D
ER
EM
ROOM #
TIME

SESSION #
Technical Program at a Glance
TUESDAY PM - OCTOBER 13, 2009
SESSION TITLES
33 Dialogue Techniques: Dialogue Versus Consultation, Comm. of Risk, Edu., Use of Web Tech. X Room 14 16:15
34 Poster Session - Low/Intermediate Level Waste X 2nd Floor 13:30
WEDNESDAY AM - OCTOBER 14, 2009
35 Panel 35 has been merged with Panel 46
36 D&D Technologies - Part 1 of 2 X Room 3B 08:30
37 D&D Radiological Characterization and Monitoring X Room 3A 08:30
38 Siting, Design, Construction, and Operation of L/ILW Disposal Facilities X Room 11C 08:30
39 L/ILW Waste Handling, Technologies, and Data Analysis - Part 1 of 3 X Room 13 08:30
40 L/ILW Waste Handling, Technologies, and Data Analysis - Part 2 of 3 X Room 13 10:45
41 Transportation and Storage of HLW, Fissile, TRU, and SNF X Room 4B 08:30
42 ER Site Characterization and Monitoring - Part 2 of 2 X Room 12 08:30
43 Uranium Mining and Milling Sites ER (Directly after Session 42) X Room 12
44 Panel: Young Generation Network (YGN) - “An Audience with…” X Room 11B 10:45
45 Poster Session Environmental Remediation/EM X 2nd Floor 08:30
WEDNESDAY PM - OCTOBER 14, 2009
46 Panel: UK NDA and Tier 1 Funding, Contracting, Subcontracting Selection and Arrangements X Room 3A 13:45
47 Panel: UMREG Panel/Roundtable X Room 3B 13:45
48 Liquid Waste Treatment Process and Experience X Room 11C 13:45
49 L/ILW Waste Handling, Technologies, and Data Analysis - Part 3 of 3 X Room 14 13:45
50 Quality Assurance and Control in Radioactive Waste Management X Room 14 16:15
51 Vitrification and Borosilicate Glass Alternatives for Immobilization X Room 4B 13:45
52 A Synopsis of Knowledge Management Systems X Room 12 13:45
53 Panel: Future Directions in Knowledge Management X Room 12 16:15
54 D&D Technologies - Part 2 of 2 X Room 11B 13:45
55 Regulatory Compliance, Radiological Surveys, and Facility Release X Room 13 13:45
56 Posters: Projects In Progress X 2nd Floor 13:30
THURSDAY AM - OCTOBER 15, 2009
57 D&D of Non-Reactor Nuclear Facilities X Room 3B 08:30
58 D&D Management Approaches and Planning Tools X Room 12 08:30
59 Safety Considerations Associated with L/ILW Management X Room 11B 10:45
60 L/ILW Treatment Technology Development and Implementation X Room 11C 08:30
61 Characterization and Performance Assessment For HLW, Fissile, TRU, and SNF X Room 13 08:30
62 Recent Developments in ER Technologies X Room 4B 08:30
63 Natural Analogues in Radwaste Disposal - Answering the Hard Questions X Room 14 08:30
LLW
HWL
D&D
ER
EM
ROOM #
TIME
15

Monday AM Technical Sessions
Monday, October 12, 2009
SESSION 1
Monday 09:00 - 12:30 Room:1
PLENARY - OPENING SESSION
Co-Chairs: Kenneth Kok, URS Washington Division (USA)
Fred Sheil, Sellafield Ltd. (UK)
Welcome to the ICEM’09 <strong>Conference</strong> —
Welcome to Liverpool —
Plenary speakers that have confirmed:
• Dr. Inés Triay, Assistant Secretary- US DOE EM Program
(USA)
• Hans Forström, Director of Nuclear Fuel Cycle and Waste
Technology IAEA (AUSTRIA)
• Stephen Henwood, Chairman, Nuclear Decommissioning
Authority (UK)
• Bill Poulson, Managing Director, Shellafield Ltd. (UK)
<strong>Conference</strong> Organization and Administration:
Gary Benda, <strong>Conference</strong> Manager (USA)
SESSION 2A
Monday 13:45 Room:3A
PANEL: ENVIRONMENTAL CLEANUP WORLDWIDE -
CHALLENGES AND OPPORTUNITIES
Co-Chairs: Ana M. Han, US DOE (USA)
James Marra, SRNS (USA)
Organizers: Kurt Gerdes, Ana Han
This panel will provide a global perspective on the current status of
environmental management in the world ...
Panelists include: Marc Butez, CEA (France); Hiroyuki Umeki,
JAEA (Japan); Myung-Jae Song, Doosan (Korea); Adrian Simper,
NDA (UK); and Samit Bhattacharyya, SRNL (USA).
SESSION 2B
Monday 16:15 Room:3A
PANEL: WILL THE LACK OF GEOLOGICAL
REPOSITORIES SLOW THE NUCLEAR RENAISSANCE
Co-Chairs: Phillip Gregory, Washington TRU Solutions (USA)
Charles McCombie, Arius Association (UK)
Organizers: Murthy Devarakonda, Charles McCombie
<strong>The</strong> continued growth in interest in expanding nuclear power program
and the continuing challenge of implementing geological disposal are
strongly related issues. New nuclear plants may be more acceptable if
“the waste problem” is seen to be solved – and thus more effort may
be devoted to this task. On the other hand, the urgent need for more,
CO2 free electricity may tempt decision makers to downplay the backend
issues. In either case, there may be direct impacts on national
disposal programs and also on the support given to multinational
disposal initiatives that may provide small and new nuclear programs
with earlier, more affordable, access to safe and secure repositories.
Panelists include: Professor W.E. (Bill) Lee, Imperial College (UK);
Hiroyuki Umeki, JAEA (Japan); Ewoud Verhoef, COVRA
(Netherlands); and Charles McCombie, Arius Association (UK).
SESSION 3
Monday 13:45 Room: 3B
HOT TOPICS AND EMERGING ISSUES IN D&D
Co-Chairs: Jas S. Devgun, Sargent & Lundy (USA)
Michele Laraia, IAEA (AUSTRIA)
Organizer: Jas Devgun
This panel will focus on current hot topics and emerging issues in the
decommissioning area worldwide. <strong>The</strong> topics being considered
include critical issues facing D&D, privatization, supply chain issues,
16
disposal issues, cost-effectiveness, loss and retention of skills, and
international cooperation and networking.
Panelists include: Dr. Jas Devgun, Sargent & Lundy LLC, (USA);
Dr. Michele Laraia, IAEA (Austria); Russ Mellor, Sellafield (UK);
Dr. Charles Miller, US Nuclear Regulatory Commission (USA); Mr.
Richard Mrowicki, NDA (UK); David Boath, AMEC (UK); and
Brad Smith, CH2M Hill (USA).
SESSION 4
Monday 13:45 Room: 12
PANEL: NATIONAL PROGRAMS FOR L/ILW
Co-Chairs: Juergen Krone, DBE TECHNOLOGY GmbH
(GERMANY)
Angie Jones, AMEC Earth & Environmental (USA)
Organizer: Angie Jones
1. UK Strategy for Nuclear Industry LLW – 16393
Matthew Clark, Joanne Fisher, NDA (UK)
2. <strong>The</strong> Role of the National Low Level Waste Repository In
Delivering New Solutions for the Management of Low Level
Wastes in the UK – 16217
Martin Walkingshaw, LLW Repository Ltd, (UK)
3. Sellafield Site Low Level Waste Management Strategy – 16234
Laurence Cook, David Loudon, Charles Mason, Sellafield
Limited, (UK)
4. Regulatory Review of Preliminary Safety Assessment for the
Baita Bihor Repository, Romania – 16031
Enrique Biurrun, Bernt Haverkamp, DBE Technology GmbH,
(Germany); Klaus-Jürgen Röhlig, Clausthal University of
Technology, (Germany)
—————— Break ——————
5. An Overview of US EPAs Current Radioactive Waste
Management Efforts – 16104
Tom Peake, Loren Setlow, Daniel Schultheisz, Ken Czyscinski,
US Environmental Protection Agency, (USA)
6. Analysis of Management and Disposal Alternatives for Low
Activity Radioactive Waste – 16192
Keith Anderson, ECC (USA)
7. Strategy and Practice in Spent Sealed Sources Management in
Belgium – 16335
Vincent De pooter, NIRAS/ONDRAF (Belgium); Marnix
Braeckeveldt, David Vanleeuw, Gunter Van Zaelen,
NIRAS/ONDRAF (Belgium)
8. Improvement of the Management of Institutional Radioactive
Waste in Slovenia – 16092
Marija Fabjan, Agency for Radwaste Management, SI-1000
(Slovenia); Jože Rojc, RŽV- Mine Žrovski vrh, (Slovenia); Koen
Lenie, Leniko, (Belgium); Yves Niels, IRE, (Belgium); Gasper
Tavar, Matjaž Stepišnik, Institut “Jožef Stefan” (Slovenia)
SESSION 5
Monday 13:45 Room: 4B
LLW CHARACTERIZATION, TREATMENT & PACKAGING
DEVELOPMENTS - PART 1 OF 2
Co-Chairs: Kapil Goyal, Los Alamos National Laboratory (USA)
Hans Codee, COVRA N.V. (NETHERLANDS)
Organizer: Kapil Goyal
1. Treatment of Irradiated Core Components from BWR and PWR
Nuclear Power Plants – 16043
Joerg Viermann, Joerg Radzuweit, Andreas Friske, GNS
Gesellschaft fuer Nuklear-Service mbH (Germany)
2. Characterization of NORM Sources in Petroleum Coke
Calcining Processes – 16314
Ian Hamilton, Donald Halter, Matthew Arno, Foxfire Scientific
(USA); Robert Berry, Foxfire Scientific, Inc. (UK)
3. Measurement of Solid-Liquid Mixtures Using Electrical
Tomography Measurement Techniques – 16088
Gary Bolton, Industrial Tomography Systems (UK); Steven
Stanley, National Nuclear Labpratory (UK)

Technical Sessions Monday PM
SESSION 6
Monday 16:15 Room: 4B
LLW CHARACTERIZATION, TREATMENT & PACKAGING
DEVELOPMENTS - PART 2 OF 2
Co-Chairs: Hans Codee, COVRA N.V. (NETHERLANDS)
Kapil Goyal, Los Alamos National Laboratory (USA)
Organizer: Angie Jones, AMEC Earth & Environmental (USA)
1. Increasing Operational Efficiency in a Radioactive Waste
Processing Plant – 16100
Tom Turner, Stuart Watson, UKAEA (UK)
2. Management of Historical Radioactive Waste – 16267
Gheorghe Dograu, Felicia Dragolici, Laura Ionascu, Gheorghe
Rotarescu, National Institute of Reserch & Development for
Physics and Nuclear Engineering-Horia Hulubei (Romania)
3. Volume Reduction of Radioactive Concrete Wastes Generated
by Dismantling Nuclear Facilities – 16165
Byung youn Min, Wang-Kyu Choi, Jung-Woo Park, Kune-Woo
Lee, Korea Atomic Energy Research institute, (Korea)
SESSION 7
Monday 13:45 Room: 11B
NATIONAL AND INTERNATIONAL ER PROGRAMS
Co-Chairs: Steve Brown, SENES Consultants (USA)
Organizer: Leo van Velzen, NRG (SWITZERLAND)
1. Expectations for Managing Contaminated Ground and
Groundwater: Developing a Common View of NDA and
Regulators – 16252
Anna Clark, Nuclear Decommissioning Authority (UK)
2. <strong>The</strong> Government of Canada’s Programmes for Radioactive
Waste Cleanup and Long-Term Management – 16133
David McCauley, Doug Metcalfe, Marcia Blanchette, Tom
Calvert, Natural Resources Canada (Canada)
3. European Radiation Survey and Site Execution Manual
(EURSSEM) – 16176
Leo P.M. van Velzen, Nuclear Research and Consultancy Group
(Switzerland); Lucien Tuenckens, Colenco Power Engineering
Ltd.(Switzerland); Marek Vasko, Decom, a.s. (Slovakia);
Kristina Kristofova, Decom a.s.(Slovakia); Igor Matejovic, Eva
Hajkova, DECOM, a.s.(Slovakia); Vladimir Daniska, Deconta,
a.s. (Slovakia)
4. IAEA - Environet: <strong>The</strong> Network on Environmental Management
and Remediation – 16421
Horst Monken-Fernandee, IAEA (AUSTRIA, Decommissioning
Authority, (UK)
SESSION 8
Monday 16:15 Room:11B
EXPERIENCES IN ER CLEAN-UP ACTIONS
Co-Chairs: Leo van Velzen, NRG (SWITZERLAND)
Art Desroiser, SEC (USA)
Organizer: Leo van Velzen
1. Safe and Compliant Management Approach to Environmental
Remediation of the Hanford Site Central Plateau – 16025*
John Lehew, CH2M HILL Plateau Remediation Company
(USA)
2. Remediation of the Site of a Former Active Handling Building
in the United Kingdom – 16041
Jack Armitage, Nuvia Limited (UK); Rowland Cornell, Nuvia
Limited (UK); Andy Staples, United Kingdom Atomic Energy
Authority (UK)
3. A Successful Remediation Project – 16400
L. Max Scott, Louisiana State University (USA)
4. Evaluation and Potential Remediation of the Industrial Norm
Legacy in Liverpool – 16096
Nigel Reeves, Gordon John, Bob Major, AMEC Nuclear Ltd.
(UK)
SESSION 9
Monday 13:45 Room: 11C
NATIONAL, MULTI-NATIONAL AND INTERNATIONAL
PROGRAMS
Co-Chairs: Mick Bacon, Health and Safety Executive (UK)
Ondrej Slavik, VUJE, a.s. (SLOVAKIA)
Organizer: Jennifer Biedscheid, Washington Division of URS
(USA)
1. <strong>The</strong> Nuclear Engineering Doctorate and NTEC CPD & Masters
Programmes: Education, Training And Research For <strong>The</strong>
Decommissioning Skillsbase. – 16395
John Roberts, <strong>The</strong> University of Manchester (UK)
2. Collaborative Retek Exchange – An Innovative Solution to the
Skills and Resource Shortage in the Nuclear Industry – 16396
Corhyn Parr, ReTek Consulting, (UK)
3. European Regional Repositories, Developing a Practical
Implementation Strategy – 16310
Ewoud Verhoef, COVRA (Netherlands) Charles McCombie,
Neil A. Chapman, Arius Association (Switzerland)
4. UK Surplus Source Disposal Programme, (SSDP) – 16097
Nigel Reeves, Gordon John, AMEC (UK)
—————— Break ——————
5. Geological Siting Regions Proposed by Nagra for the L/ILW and
the HLW Repositories as the First Step in the Application of the
Recently Established Swiss Site Selection Plan – 16295*
Jürg W. Schneider, Andreas Gautschi, Piet Zuidema, Nagra
(Switzerland)
6. A Summary of Radiological Waste Disposal Practices in <strong>The</strong>
United States and the United Kingdom – 16379
Victoria Maranville, AMEC Earth and Envorinmental (USA);
Richard McGrath, AMEC Nuclear (UK)
7. Best in Class Project and Contract Management Initiative at the
Department of Energy’s Office of Environmental Management –
16062
Scott Van Camp, U.S. Dept. of Energy (USA); Mike Deiters,
Project Time & Cost, Inc. (USA)
8. Education and Industry Partnership: A Case Study of Co-
Delivery – 16065
Timothy Mercer, John Tyndall Institute for Nuclear Research
(UK); Jonathan Francis, University of Central Lancashire (UK)
SESSION 10
Monday 13:45 Room: 13
EM LIFE-CYCLE ECONOMICS AND COST-BENEFIT
ANALYSIS
Co-Chairs: Charles Negin, Project Enhancement Corp (USA)
Terry Wickland, Nuclear Filter Technologies (USA)
Organizer: Jennifer Biedscheid, Washington Division of URS
(USA)
1. UK Nuclear Decommissioning Authority - Value Framework, its
Development and Role in Decision Making – 16399
Mark Wareing, NDA (UK)
2. Strategic Environmental Assessment for UK LLW Management
– 16392
Andrew Craze, Matthew Clark, NDA (UK); Pete Davis, Entec
UL Ltd. (UK)
3. <strong>The</strong> Belgian Inventory of Nuclear Liabilities – 16317
Christian Cosemans, Jacques Cantarella, Gerda Bal,
ONDRAF/NIRAS (Belgium)
4. Financial Risks of Post-Closure Custodial Care for the Barnwell
Radioactive Waste Disposal Facility – 16155
Robert Baird, Washington Division, URS Corporation (USA);
William Newberry, South Carolina Energy Office (USA)
17

Monday PM Technical Sessions
SESSION 11A
Monday 16:15 Room: 13
PANEL: YGN ROUNDTABLE “AN AUDIENCE WITH...”
Co-Chairs: Corhyn Parr, Nuclear Enterprise Ltd. (UK)
Chris Williams, VT Nuclear Services (UK)
Organizers: Corhyn Parr, Chris Williams
This round table discussion was developed due to the fact that YGN
members in the UK don’t know where to turn for career advice and
feel that there is a glass ceiling for progression dependent on age
which we want to investigate.
<strong>The</strong> session will be led by Russ Mellor, Decommissioning Director at
Sellafield Ltd and Miranda Kirschel, Business Development Director
at CH2MHILL, <strong>International</strong> Nuclear Services. Both have had varied
and interesting career paths and are happy to share their experiences
with younger members of industry in a relaxed round table
environment with plenty of time for questions and discussion. <strong>The</strong>
session is aimed at the encouragement for career development of
younger members of industry and to investigate if there is a glass
ceiling stopping career progression in UK or elsewhere in the world.
SESSION 11B
Monday: After Session 11A Room: 13
YGN GENERAL MEETING
Co-Chairs: Corhyn Parr, Nuclear Enterprise Ltd. (UK)
Chris Williams, VT Nuclear Services (UK)
Organizers: Corhyn Parr, Chris Williams
A general YGN Meeting will be conducted to canvass canvass view of
the Younger members of the industry, exchange knowledge across
companies, and grow the YGN network through the conference
attendees. This meeting will be used to share best practice, and
develop new ideas to progress the aims and objectives of the YGN in
the future.
Agenda: 1) Introductions; 2) Explanation of YGN Aims and
Objectives; 3) Discussion on Output of YGN Questionnaire; 4)
Sharing of <strong>International</strong> YGN Activities and Events; 5) Personal
Development and Career Progression; 6) Education and Training
Initiatives; 7) Communications across the YGN Network; 8) External
Communications to wider industry and 9) Future Plans and New
Initiatives.
SESSION 12
Monday 13:30 Room: 2nd Floor
POSTER SESSION — SPENT FUEL, FISSILE, TRANSURANIC
AND HIGH LEVEL WASTE MANAGEMENT
Co-Chairs: Phillip Gregory, Washington TRU Solutions (USA)
Gerry McGill, AMEC (UK)
Organizers: Murthy Devarakonda, Gerry McGill
A. Selective Uptake of Palladium from High-Level Liquid Wastes
by Hybrid Microcapsules Enclosed with Insoluble Ferrocyanides
– 16382
Hitoshi Mimura, Takashi Sakakibara, Wu Yan, Yuichi Niibori,
Toyko University (Japan); Shin-ichi Koyama, Takashi Ohnishi,
Japan Atomic Energy Agency (Japan).
B. Up-take of 14C-Acetic Acid by Rice Plant Related to Root
Function and Microbial Activity in Rhizosphere – 16111
Shinichi Ogiyama, National Institute of Radiological Sciences
(Japan); Nobuyoshi Ishii, Shigeo Uchida, National Institute of
Radiological Sciences (Japan)
C. Characteristics on the SAP- Based Wasteform Containing
Radioactive Molten Salt Waste – 16137
Hwan-Seo Park, In-Tae Kim, Hwan-Young Kim; Han-Soo Lee,
Korea Atomic Energy Research Institute (Korea)
D. Realistic Integration of Sorption Processes in Transport
Programs for Long-term Safety Analysis – 16370
Madlen Stockmann, FZ Dresden-Rossendorf (Germany);
Vinzenz Brendler, Forschungszentrum Dresden-Rossendorf e.
(Germany) Ulrich Noseck, Gesellschaft für Anlagen- und
Reaktorsicherheit (GRS) mbH (Germany)
18
E. Emerging Challenges in Nuclear Waste Management in India in
View of its Expansion Programme – 16364
Murty.S Ganti, Andhra University (India)
F. Towards an Implementing Geological Disposal Technology
Platform in Europe – 16365
Marjatta Palmu, Posiva Oy, (Finland); Torsten Eng, SKB
(Sweden)
G. WVP Melter Analysis and Modelling for Lifetime Extension –
16209*
Clare Booth, Sellafield Sites (UK); Mark D’Vaz, Sellafield Ltd
(UK)
H. FEBEX in Situ Test - Showing the Value of Very Long Term
(>10 years) Experiments – 16422*
Irina Gaus, NAGRA (Switzerland); Erik Thurner, SKB
(Sweden); Marjut Vahanen, Posiva, (Finland); Pedro Luis
Martín Martín, CIEMAT (Spain); Juan Carlos Mayor, ENRESA
(Spain); Jose Luis García-Siñeriz, Aitemin, (Spain); Antonio
Gens, UPC (Spain)
I. Partitioning Ratios Among Solid-, Liquid-, and Gas-phases for
C-14 Labeled Sodium Acetate in Paddy and Upland Soils –
16112*
Nobuyoshi Ishii, National Institute of Radiological Sciences
(Japan)
J. A Study on the Once-through Back-end Fuel Cycle Scenario –
16129
Yoon Hee Lee, Kunjai Lee,Kunjai Lee, KAIST (Korea);
Jongsoon Song, Chosun University (Korea)
K. Aerodynamic Resistance of a New Filters for Cs-137 Vapour
Capture at High Temperature – 16146*
Albert Aloy, Alexander Strelnikov, Khlopin Radium Institute
(Russia); Sergey Rovny, Nikolay Pyatin, PA “Mayak” (Russia)
L. Separation of Rare Earth Precipitates from LiCl-KCl Eutectic
Salts by a Distillation at a Reduced Pressure – 16162
Hee-Chul Eun, Korea Atomic Energy Research
Institute(Korea); Hee-Chul Yang, Yung-Zun Cho, Han-Soo Lee,
In-Tae Kim, Korea Atomic Energy Research Institute (Korea)
M. Development of a LCC Structure for the Recovery of Actinides
from Molten Salt – 16167*
Seungwoo Paek, Si-Hyung Kim, Dal-Seong Yoon, Joon-Bo
Shim, Do-Hee Ahn, Han-Soo Lee, Korea Atomic Energy
Research Institute (Korea)
N. <strong>The</strong> Standard- Legal Regulation of SNF Import from Foreign
Reactors in the Russian Federation – 16171
Nekhozhin Mikhail, FSUE FCNRS (Russia)
Tuesday, October 13, 2009
SESSION 13
Tuesday 08:30 Room: 3B
PANEL: EMERGING ISSUES IN THE MANAGEMENT FOR
L/ILW
Co-Chairs: Angie Jones, AMEC Earth & Environmental (USA)
Andy Baker, Andy Baker Consulting Ltd. (UK)
Organizers: Angie Jones, Andy Baker
This panel will focus on strategies for the management of all low and
intermediate level waste (L/ILW). Based on experience in different
national programs, it will discuss various options and their merits for
managing L/ILW. It will consider the definition of different categories
of L/ILW and their potential routes for disposal including waste of
very low activity, often arising in high volumes as contaminated land
or from decommissioning.
Panelists include: Mr. Phil Davies, NDA, Head of National Waste
Mgmt. Strategy (UK); Mr. Hans Forström, Director, Nuclear Fuel
Cycle & Waste Technology - IAEA (Austria); Dr. S. D. Misra,
Director of Nuclear Recycle Group, BARC (India); Mr. Michel
Dutzer, Director Industrielle, ANDRA (France). and Mr. David
Bennett, Strategic Policy Manager, Environmental Agency of
England and Wales (UK).

Technical Sessions Tuesday AM
SESSION 14
Tuesday 08:30 Room: 12
PANEL: INTERNATIONAL DECOMMISSIONING NETWORK
Co-Chairs: Michele Laraia, IAEA (AUSTRIA)
Takeshi Ishikura, <strong>The</strong> Institute of Applied Energy
(JAPAN)
Organizer: Michele Laraia
This panel will focus on IAEA’s <strong>International</strong> Decommissioning
Network (IDN). In this session, IDN-involved organizations will be
invited to report on their experience in co-operating with the IAEA in
the field of decommissioning. <strong>The</strong> panel will be introduced by an
overview of progress achieved and plans developed under the IDN.
Since the IDN is intended to function as a loose “Network of
Networks”, other presentations in this session should include work
involving bilateral / multinational agreements carried out by non-
IAEA organizations which form complementary “Networks”. Active
discussion can be expected to ensure dissemination of information
about and support for the IDN concept by organizations not involved
yet.
Panelists include: Staffan Linsdkog, SKI (Sweden); Sean Bushart,
EPRI (USA); Leopold Weil, Federal Office for Radiation Protection
(BfS) (Germany); Maria Lindberg, Studsvik UK Ltd. (UK); Doug
Metcalfe, Natural Resources Canada, (Canada); and Michele Laraia,
<strong>International</strong> Atomic Energy Agency (IAEA) (Austria).
SESSION 15
Tuesday 08:30 Room: 4B
DISPOSAL SITE AND WASTE FORM CHARACTERIZATION
AND PERFORMANCE ASSESSMENT
Co-Chairs: Ed Bentz, E.J. Bentz & Associate (USA)
Ian Beadle, AMEC Nuclear UK Limited (UK)
Organizers: Ian Beadle, Angie Jones, AMEC Earth &
Environmental (USA)
1. A Preliminary Postclosure Safety Assessment of OPGs Proposed
L&ILW Deep Geologic Repository, Canada – 16289
Richard Little, Quintessa Limited (UK); John Avis, Nicola
Calder, Intera Engineering Limited (Canada); Nava Garisto,
Senes Consultants Limited (Canada); Paul Gierszewski, Helen
Leung, Nuclear Waste Management Organization (Canada);
Laura Limer, James Penfold, George Towler, Russell Walke,
Robert Walsh, Quintessa Limited (UK)
2. Numerical Assessment of the Long-Term Safety of the
Morsleben Repository for Low- and Intermediate-Level
Radioactive Waste – 16346
Juergen Wollrath, Juergen Preuss, Bundesamt fuer
Strahlenschutz (BfS) (Germany); Dirk-Alexander Becker, Joerg
Moenig, Gesellschaft fuer Anlagen- und Reaktorsicherheit
(GRS) mbH (UK)
3. <strong>The</strong> Development and Use of the GGM and T2GGM Codes for
the Postclosure Safety Assessment of OPGs Proposed L&ILW
Deep Geologic Repository - Canada – 16291
Paul Suckling, Quintessa Limited (UK); Nicola Calder, Intera
Engineering Limited (Canada); Paul Humphreys, University of
Huddersfield (UK); Fraser King, Integrity Corrosion Consulting
Limited (Canada); Helen Leung, Nuclear Waste Management
Organization (Canada)
4. Curing Time Effect on the Fraction Of 137CS from Immobilized
Radioactive Evaporator Sludge by Cement – 16329
Ilija Plecas, Slavko Dimovic, Vinca Institute (Serbia)
—————— Break ——————
5. Modelling Long-Term Corrosion of Cemented Waste Forms in
Salt Brines – 16202
Bernhard Kienzler, Volker Metz, Forschungszentrum Karlsruhe
(Germany)
6. Coupling Time-Dependent Sorption Values of Degrading
Concrete with a Radionuclide Migration Model – 16220
Janez Perko, Dirk Mallants, Diederik Jacques, Lian Wang,
Belgian Nuclear Research Centre SCK-CEN (Belgium)
7. A Numerical Study of Factors Affecting Radioactive Gas
Migration in the Far-Field – 16273*
Elina Kuitunen, Michael A. Hicks, <strong>The</strong> University of
Manchester (UK)
SESSION 16
Tuesday 08:30 Room: 3A
NATIONAL AND INTERNATIONAL PROGRAMS FOR SPENT
FUEL, FISSILE, TRU, AND HLW MANAGEMENT
Co-Chairs: Natraj Iyer, SRNL (USA)
Hans Codee, COVRA N.V. (NETHERLANDS)
Organizer: Hans Codee
1. NUMO-RMS: a Practical Requirements Management System
for the Long-Term Management of the Deep Geological
Disposal Project – 16304
Hiroyoshi Ueda, Satoru Suzuki, Katsuhiko Ishiguro, Nuclear
Waste Management Organization of Japan (NUMO) (Japan);
Kiyoshi Oyamada, JGC Corporation (Japan); Shoko Yashio,
Obayashi Corporation (Japan); Matt White, Roger Wilmot,
Galson Sciences Limited (UK)
2. Strategic Plan for the Management of Spent Nuclear Plan –
16024*
Hitesh Nigam, Edgardo (Gary) DeLeon, Department of Energy
(USA)
3. Disposal Technologies for Spent Fuel from German Nuclear
Power Plants – 16028
Reinhold Graf, GNS mbH (Germany); Wolfgang Filbert, DBE
Technology GmbH(Germany); Klaus-Jürgen Brammer, GNS,
Gesellschaft für Nuklear-Service mbH (Germany); Wilhelm
Bollingerfehr, DBE Technology GmbH (Germany)
4. Characteristics of the Spent Fuel Generated in Korea – 16227
Donghak Kook, Jongwon Choi, Heuijoo Choi, Dongkeun Cho,
KAERI (Korea)
—————— Break ——————
5. New Safety Concept for Geological Disposal in Japan – 16339
Kazumi Kitayama, Nuclear Waste Management Organization of
Japan (NUMO) (Japan)
6. Proposals on Management of AMB SNF – 16169*
A.V. Yescherkin, V.A. Zotov, S,V. Kazakov, M.A. Nekhozhin, V.P.
Smirnov, FSUE FCNRS (Russia); D.A. Goncharov, OOO NPF
Sosny, Dmitrovgrad; E.G. Kudryavtsev, A.V. Khapyorskaya,
Rosatom; Kovacz Y., Hamvas, I., NPS Paks, (Hungary)
7. An Overview on the National Radwastes Management Strategy
into the Context of the Nuclear Program Development – 16356
Panait Adrian, Maria Radu,Gheorghr Barariu, Center of
Technology and Engineering for Nuclear Objectives (CITON)
(Romania), Gheorghe Negut, Cristian Litescu, Nuclear Agency
for Radwaste Management (Romania)
SESSION 17
Tuesday 08:30 Room: 13
HLW CHARACTERIZATION / RECENT ADVANCES IN HLW
TREATMENT SYSTEMS
Co-Chairs: Pierre Van Iseghem, SCK.CEN, Mol (BELGIUM)
David Hobbs, SRNL (USA)
Organizer: Pierre Van Iseghem
1. Separation of Fission Products and Actinides from Savannah
River Site High-Level Nuclear Wastes – 16174
David Hobbs, Thomas Peters, Michael Poirier, Fernando
Fondeur, Charles Nash, Samuel Fink, Savannah River
NationalLaboratory (USA)
2. Safety Assessment of Geological Disposal of High-Level
Radioactive Waste in Boom Clay: Relation with the
Radionuclide Inventory – 16418
Pierre Van Iseghem, Jan Marivoet, SCK.CEN (Belgium)
3. Design of Pyroprocess Digital Mockup and Workspace Analysis
of Devices – 16140*
Hee Seoung Park, Chang-Hwan Choi, Sung-Hyun Kim, Byung-
Seok Park, Ki-Ho Kim, Ho-Dong Kim, Korea Atomic Energy
Research Institute (Korea)
19

Tuesday AM Technical Sessions
4. Designing a New Highly Active Liquor Evaporator – 16075
Paul Robson, Emma Candy, Sellafield Limited (UK)
—————— Break ——————
5. <strong>The</strong> Hydrolysis of Hydroxamic Acid Complexants in the
Presence of Non-Oxidizing Metal Ions – 16230*
Fabrice Andrieux, University of Central Lancashire (UK);
Colin Boxall, Lancaster University (UK); Iain May, Los Alamos
National laboratory (UK); Robin J Taylor, National Nuclear
Laboratory (UK)
6. Developing Ceramic Based Technology for the Immobilisation
of Waste on the Sellafield Site – 16049
Charlie Scales, Ewan Maddrell, National Nuclear Laboratory
(UK); Mark Dowson, Sellafield Ltd. (UK)
7. <strong>The</strong> Use of Hot-Isostatic Pressing to Process Nuclear Waste
Forms – 16253
Martin Stewart, Sam Moricca, Tina Eddowes, Yingjie Zhang,
Eric Vance, Gregory Lumpkin, Melody Carter, ANSTO
(Australia); Mike James, Mark Dowson, Sellafield (UK)
8. Design Innovations for the Management of Alpha Contaminated
Unserviceable Glove Boxes – 16224
R.K. Gupta, D.S Sandhanshive, S.R. Shendge, A.K. Singh,
M.N.B. Pillai, Arun Kumar, PP Mazumdar, Bhabha Atomic
Research Centr (India)
SESSION 18
Tuesday 08:30 Room: 11C
D&D OF POWER REACTORS AND RESEARCH REACTORS
Co-Chairs: Jas S. Devgun, Sargent & Lundy (USA)
David Boath, AMEC (UK)
Organizer: Jas Devgun
1. Transport of the Reactor Pressure Vessels in the Greifswald
Nuclear Power Plant – 16012
Ralf Borchardt, Energiewerke Nord GmbH (Germany)
2. Technology Development for Decommissioning in FUGEN and
Current Status – 16108
Koichi Kitamura, Japan Atomic Energy Agency (Japan);
Kazuya Sano, Yasuyuki Nakamura, Akira Matsushima, Masahiro
Ishiyama, Hidehiko Matsuo, Masashi Tezuka, Takahiro Haneda,
Japan Atomic Energy Agency (Japan); Reginald Coomans,
Tecnubel (Belgium)
3. Seeking the Optimum Solution for Reactor Decommissioning
Waste – 16391
Lisa Hughes, NDA (UK)
4. Modelling of Radiation Fields and Estimation of Doses during
Dismantling of RBMK-1500 Reactor Emergency Core Cooling
System – 16247
Povilas Poskas, Audrius Simonis, Lithuanian Energy Institute
(Lithuania)
—————— Break ——————
5. Dismantling the Reactor Containment of Germany´s First NPP –
16272
Ludger Eickelpasch, NUKEM Technologies GmbH (Germany)
6. Use of Remote Equipment in Reactor Decommissioning –
16326
Scott Martin, Matt Cole, Scott Adams, S.A.Robotics (USA)
7. Experience in Chemical Decontamination of PWR Systems and
Components – 16274
Claude Steinkuhler, DDR Consult (Belgium); Koen Lenie,
Reginald Coomans, Tecnubel (Belgium)
8. Assessment of Decommissioning Waste for Korean Standard
Nuclear Power Plant – 16126
Jai-Hoon Jung, Han-Jung Na, Jung-Su Park, Byung-Sik Lee,
Jong-Hyuck Lee, KOPEC (Korea)
20
SESSION 19
Tuesday 08:30 Room: 14
GLOBAL PARTNERING IN INTERNATIONAL CLEAN-UP
PROGRAMS
Co-Chairs: Michael Cull, Teledyne Brown Engineering (USA)
Mark Gerchikov, AMEC NSS (CANADA)
Organizers: Michael Cull, Mark Gerchikov
1. Decommissioning and Dismantling Solution Development for
Volodarsky Civil Nuclear Fleet Support Ship – 16386
Konstantin N. Koulikov, Rinat A. Nisamutdinov, NIPTB
ONEGA OAO (Russia); Andrey N. Abramov, Atomflot FGUP
(Russia), Anatoly I. Tsubanikov, Aspect-Conversion ANO
(Russia)
2. Dismantlement of Nuclear Powered Submarines in Russia –
16414
Alexey Maltsev, JSC SC Zvyozdochka (Russia)
3. Environmental Assessments of Nuclear Submarine
Decommissioning in the Russian Far East – 16360
Michael Washer, Department of Foreign Affairs and
<strong>International</strong> Trade (Canada); Mark Gerchikov, AMEC NSS
(Canada); Michael Cull, Teledyne Brown Engineering (USA)
Konstantin Koulikov, NIPTB Onega (Russia)
4. Remediation of Gremikha Coastal Maintenance Base in North-
West Russia – 16279
Boris S. Stepennov, Kurtchatov Institution (Russia); Alexandre
Gorbatchev, CEA (France); Lucien Pillette-Cousin, AREVA TA
(France)
SESSION 20
Tuesday 10:45 Room: 11B
PANEL: GLOBAL PARTNERING IN INTERNATIONAL
WASTE AND CLEANUP PROGRAMS
Co-Chairs: Michael Cull, Teledyne Brown Engineering, Inc.
(USA)
Mark Gerchikov, AMEC NSS (CANADA)
Organizers: Michael Cull, Mark Gerchikov
This panel will provide a global perspective on the status of the cleanup
of nuclear legacy sites in the North West and Far East Russia and
lessons learned by key participants of the Global Partnership Program.
<strong>The</strong> speakers will discuss best practice in international cooperation,
meeting regulatory requirements and approaches to ensure safe
management of spent nuclear fuel and radioactive waste. Speakers in
this session will discuss their Global Partnership activities, and
explore opportunities for future international collaboration.
Panelists include: Michael Washer, Department of Foreign Affairs
and <strong>International</strong> Trade (Canada); Aleksey Maltzev, FSUE
Zvyozdochka (Russia) and Konstantin Kulikov, NIPTB Onega
(Russia); Sergey Kazakov, Director of the Federal Nuclear Safety
Centre (Russia); and Lucien Pillette-Cousin, AREVA (France)
SESSION 21
Tuesday 10:45 Room: 14
ENVIROMENTAL MANAGEMENT HEALTH AND SAFETY
ISSUES
Co-Chairs: Kenneth Kok, URS - Washington Division
Safety Management Solutions (USA)
Paul Gubanc, URS - Washington Division Safety
Management Solutions (USA)
Organizer: Kenneth Kok
1. Dose Assesment of Personnel Handling Conditioned
Radioactive Waste – 16149
Michal Panik, Matej Zachar, Vladimir Necas, Slovak University
of Technology in Bratislava (Slovakia)

Technical Sessions Tuesday AM
2. Risk Analysis and Cost-Benefit Analysis of Remedial Actions in
the Central Asia: Amydarya and Syrdarya Rivers Basins
Transboundary Pollution due to Uranium Mining Industry –
16187
Vladimir Georgievskiy, Russian Research Center “Kurchatov
Insitute” (Russia)
3. Parametric Studies for Nuclear Criticality Safety Using
Microsoft Excel – 16404
Michael Crouse, URS - Washington Division (USA)
4. Processing and Conditionning of Radioactive Sludge – 16417
Olivier Lemaire, Bouygues Construction Services Nucléaires
(France); Bertrand Lantes, EDF, (France); Christophe Le-
Nagard, Bouygues Construction Services Nucléaires (France)
SESSION 22
Tuesday 08:30 Room: 2nd Floor
POSTER SESSION — FACILITY DECONTAMINATION AND
DECOMMISSIONING
Co-Chairs: Jean-Marie Cuchet, Belgonucleaire (BELGIUM)
Arthur Desrosiers, Safety and Ecology Corporation
(USA)
Organizers: Jas Devgun, Michael Laraia
A. Building 18: Operating Feedback from Cleaning and
Dismantling of Glove Boxes and Shielding Lines – 16046
Michel Jeanjacques, Marie Pierre Bremond, Laurent Gautier,
Guy Viellard, Eric Pichereau, David Estivié, Commissariat à
l’Energie Atomique (France)
B. Automated Vehicle and Waste Package Survey System – 16223
Arthur Desrosiers, Phillip Mann, Safety and Ecology
Corporation (USA)
C. Technical Performance Characterization of Fourier Transform
Profilometry for Quantiative Waste Volume Determination under
Hanford Waste Tank Conditions – 16281
David Monts, Ping-Rey Jang, Zhiling Long, Olin Norton, Walter
Okhuysen, Yi Su, Charles Waggoner, Mississippi State University
(USA)
D. <strong>The</strong> Emergence of Sustainable Practice within
Decommissioning – 16059
David Adamson, Sellafield Limited (UK); Jonathan Francis,
University of Central Lancashire (UK)
E. CFD Studies of Vortex Amplifier Design In <strong>The</strong> Context Of
Sellafield Nuclear Operations – 16061
Martin J Birch, John Tyndall Institute for Nuclear Research
(UK); Darren Parker, Land Securities Trillium (UK); Jonathan
Francis, University of Central Lancashire (UK); Raymond Doig,
Sellafield Limited (UK); G. Zhang, <strong>The</strong> University of
Manchester (UK)
F. Decommissioning of a Uranium Conversion Plant and a Low
Level Radioactive Waste for a Long Term Disposal – 16071
Yun D. Choi, D.S. Hwang, U.S. Chung, Korea Atomic Energy
Research Institute (Korea)
G. Rehabilitation Project for Podolsk Nonferrous Metals Plant –
16136
Alexander V. Chesnokov, Victor G. Volkov, Anatoly Volkovich,
Alexey Lemus, Vitaly Pavlenko, Sergey Semenov, Russian
Research Center “Kurchatov Institute”, (Russia); Maxim Gizay,
Sergey Krahotkin, FSUE Federal Property Management Center
(Russia)
H. Remote Radiation Sensor Based on Epoxy Resin and Optical
Fiber for Monitoring of High-level Decommissioning Facilities
– 16160
Bum-Kyoung Seo, Chan-Hee Park, Dong-Gyu Lee, Kune-Woo
Lee, Korea Atomic Energy Research Institute (Korea)
I. Algorithmisation of Dismantling Techniques in Standardised
Decommissioning
Costing Using the Standardised Cost List – 16201
Peter Bezak, DECOM, a.s. (Slovakia); Vladimír Daniaka,
Deconta, a.s.(Slovakia); Ivan Rehak, Decom, a.s. (Slovakia);
Vladimir Necas, Slovak University of Technology in Bratislava
(Slovakia)
J. <strong>The</strong>rmal Cutting Technologies for Decommissioning of Nuclear
Facilities – 16297
Harald Bienia, NUKEM Technologies GmbH (Germany)
K. Involvement of ANDRAD in Endorsement of Decommissioning
Documentation of Nuclear Facilities in Romania – 16315
Marin Dinca, National Agency for Radioactive Waste
(Romania)
L. Visualization of Radioactive Sources without Gamma-Radiation
with UV Imaging Systems – 16145
Oleg Ivanov, Alexey Danilovich, Vyacheslav Stepanov, Sergey
Smirnov, RRC Kurchatov Institute (Russia); Anatoly Volkovich,
Russian Research Center “Kurchatov Institute”, (Russia)
M. OXIPROBE - A Non Destructive Tool for Determining Steam
Generator Oxide Characteristics – 16250
John P. Krasznai, Kinectrics Inc. (Canada)
N. Methods of Control of Inaccuracy in Calculation of Nuclear
Power Plant Decommissioning Parameters – 16383
Frantisek Ondra, DECOM, a.s.,(Slovakia); Vladimír Daniaka,
Deconta, a.s.,(Slovakia); Ivan Rehak, Decom, a.s., (Slovakia);
Vladimir Necas, Slovak University of Technology in Bratislava
(Slovakia)
SESSION 23
Tuesday 13:45 Room: 3A
PANEL: CURRENT IAEA ACTIVITIES IN PREDISPOSAL
MANAGEMENT OF L/IL RADIOACTIVE WASTE
Co-Chairs: Zoran Drace, IAEA (AUSTRIA)
Angie Jones AMEC Earth & Environmental (USA)
Organizers: Zoran Drace, Angie Jones
This panel will focus on Waste Technology Section (WTS) of the
<strong>International</strong> Atomic Energy Agency (IAEA) which has a dedicated
program focused on waste predisposal activities. <strong>The</strong> objective of this
program is to strengthen the capability of Member States to properly
and safely process and store radioactive waste. A range of activities
are included in this program to provide guidance on selection and
implementation of waste management strategies, to provide
information and guidance on best practices and technologies for waste
minimization, pre-treatment, treatment, conditioning, packaging,
transportation and storage, to support research and development on
new pre-disposal technologies, etc. This panel will provide a forum
for the exchange of scientific and technical information and guidance
on pre-disposal radioactive waste management with focus on current
activities. <strong>The</strong> following topics will be discussed by our panel with an
opportunity for interaction with the audience.
Panelists and Topics include: Dr. Antonio Morales Leon -
Approach to Development of Waste Acceptance Criteria for all
Individual Waste Management Steps: Pre-treatment to Disposal;
Zoran Drace - Economics of Radioactive Waste Management - Cost
Calculations and Approach to Costing of Future Obligations (Liability
Assessment); Dr. Antonio Morales Leon - Standardized
Methodology for Waste Management Assessments - An Optimized
Approach to Establish Current and Future Needs and to Select
Adequate Technical Options; Dr. Sustanta Kumar - Modular and
Mobile Waste Processing Facilities; Zoran Drace - Long-term
Storage for L&IL and HL Waste - Technical Considerations; Zoran
Drace/Dr. Antonio Morales Leon - Mixed Waste Processing/Storage
and Disposal; Dr. Antonio Morales Leon - IAEA Network for
Radioactive Waste Characterization - Processing/Storage/Disposal.
SESSION 24
Tuesday 13:45 Room: 3B
NATIONAL AND INTERNATIONAL D&D PROGRAMS
Co-Chairs: Ernest Warnecke - (BfS) (GERMANY) -
Grant Koroll, AECL (CANADA)
Organizers: Jas Devgun, Michael Laraia
1. Decommissioning in the United States - Past, Present and Future
– 16318
Jas S. Devgun, Sargent & Lundy (USA)
2. Decommissioning Strategies Worldwide: A Re-Visited Overview
of Relevant Factors – 16016
Michele Laraia, <strong>International</strong> Atomic Energy Agency (IAEA)
(Austria)
21

Tuesday PM Technical Sessions
3. A Nationwide Modeling Approach to Decommissioning – 16182
Bernard Kelly, University of Manchester (UK); Paul E Mort,
Sellafield Ltd. (UK); Andrew J Lowe, University of Manchester
(UK)
4. Implementation and Ongoing Development of a Comprehensive
Program to Deal with Canadas Nuclear Legacy Liabilities –
16039
Douglas Metcalfe, Pui Wai Yuen, David McCauley, Natural
Resources Canada (Canada); Sheila Brooks, Joan Miller,
Michael Stephens, Atomic Energy of Canada Limited (Canada)
—————— Break ——————
5. <strong>The</strong> Swedish Program for Future D&D of Nuclear Power Plants
– 16143*
Jan Carlsson, Swedish Nuclear Fuel and Waste Management
Co (SKB) (Sweden)
6. AREVA Decommissioning Strategy and Programme – 16036
Guy Decobert, AREVA (France) Arnaud Gay, AREVA NC
(France)
7. Nuclear Power Plant Decommissioning in Germany - Projects,
Regulation and Experience – 16359
Leopold Weil, Federal Office for Radiation Protection (BfS)
(Germany); Bernd Rehs, Federal Office for Radiation
Protection (Germany)
8. Variation of Light Water Reactor Decommissioning Strategies in
Japan – 16113*
Takeshi Ishikura, Shigenbu Hirusawa, <strong>The</strong> Institute of Applied
Energy (Japan); Yoshihiko Horikawa, <strong>The</strong> Kansai Electric
Power Company (Japan)
SESSION 25
Tuesday 13:45 Room: 4B
TREATMENT, MANAGEMENT AND RECYCLE OF D&D
MATERIALS
Co-Chairs: Maria Lindberg, Studsvik UK Ltd (UK)
Leopold Weil, Federal Office for Radiation Protection
(BfS) (GERMANY)
Organizers: Maria Linberg, Leopold Weil
1. Waste Reduction by Re-Use of Low Activated Material – 16035
Ulrich Ehrlicher, Heinz Pauli, Paul Scherrer Institut
(Switzerland)
2. Analytical Methodology for Optimization of Waste Management
Scenarios in Nuclear Installation Decommissioning Process –
16148
Matej Zachar, Slovak University of Technology in Bratislava
(Slovakia); Vladimir Daniska, Deconta, a.s. (Slovakia); Ivan
Rehak, Marek Vasko, Decom, a.s.(Slovakia); Vladimir Necas,
Slovak University of Technology in Bratislava (Slovakia)
3. Characterisation of Reactor Graphite to Inform Strategies for
Disposal of Reactor Decommissioning Waste – 16389
Andrew Hetherington, Phil Davies, NDA (UK)
4. Demonstration of UK ILW Treatment by GeoMelt Vitrification –
16105
Keith Witwer, Kevin Finucane, Eric Dysland, AMEC, GeoMelt
Division (USA)
SESSION 26
Tuesday 16:15 Room:4B
D&D UPDATE AND MANAGEMENT ISSUES
Co-Chairs: Anthony Banford, NNL (UK)
Mark Lesinski, Magnox South Ltd. (UK)
Organizers: Anthony Banford, Mark Lesinski
1. Renewing the Focus on Decommissioning: Bringing a New
Management Perspective to Sellafield – 16243
Russ A Mellor, Sellafield Ltd (UK)
2. Embedding Nuclear, Environmental and Safety Measures from
Design through to Decommissioning – 16212*
Jack Williamson, Sellafield Ltd, Seascale (UK)
3. Optimising the UK Waste Management Programme Using
Inventory Modeling – 16394
Mervin McMinn, NDA (USA)
22
4. Innovative Highly Selective Removal of Cesium and Strontium
Utilizing a Newly Developed Class of Inorganic Ion Specific
Media – 16221
Mark Denton, Kurion, Inc., (USA) Dr. Mercouri Kanatzidis,
Northwestern University (NWU) (USA)
5. Plans and the Basic Technical Decisions on SNF Removal from
Andreeva Bay – 16170*
Nekhozhin Mikhil, FSUE FCNRS (Russia)
SESSION 27
Tuesday 13:45 Room: 11B
WASTE MINIMIZATION, AVOIDANCE AND RECYCLING
Co-Chairs: Sean Bushart, Electric Power Research Institute
(USA)
David Wallace, CDM (USA)
Organizers: Sean Bushart, David Wallace
1. A Model for a National Low Level Waste Program – 16372
James Blankenhorn, URS - Washington Division (USA)
2. CEAs Contaminated Lead Recycling Routes – 16011
Marc Butez, Frédéric Hornung, CEA (France)
3. WASAN: A Structured Methodology for the Minimisation of
Avoidable Waste – 16347
Neil Blundell, Nuclear Installations Inspectorate (UK); Duncan
Shaw, Aston Business School (UK)
4. Delivering Step Change Improvements to UK Low Level Waste
Strategy – 16188
Jason Dean, National Nuclear Laboratory (UK); David
Rossiter, Low Level Waste Repository (UK)
—————— Break ——————
5. BPEO/BPM in Recycling of Low Level Waste Metal in the UK
– 16210
Joe Robinson, Kevin Dodd, Maria Lindberg, Simon Dickson;
Mike McMullen, Studsvik (UK)
6. External Ddisposal of 4 Steam Generators out of the
Decommissioning of the Nuclear Power Plant Stade (KKS) –
16045
Martin Beverungen, GNS Gesellschaft für Nuklear-Service
mbH (Germany)
7. Factors Influencing the Performance and Lifetime of Fibrous
Glass and Metal Media HEPA Filters – 16285
Charles Waggoner, Michael Parsons, Mississippi State
University (USA)
8. <strong>International</strong> Radioactive Metals Recovery, Trans-Frontier
Shipment and Processing for Beneficial Reuse – 16303*
Al Johnson, Magnox South (UK)
SESSION 28
Tuesday 13:45 Room: 11C
REPOSITORY PROGRAMS: SITE SELECTION &
CHARACTERIZATION, UNDERGROUND RESEARCH LABS,
ENGINEERING & GEOLOGICAL BARRIERS
Co-Chairs: Pierre Van Iseghem, SCK•CEN (BELGIUM)
Bernhard Kienzler, Forschungszentrum Karlsruhe
(GERMANY)
Organizer: Pierre Van Iseghem
1. Global Developments in Multinational Initiatives at the Back
End of the Nuclear Fuel Cycle – 16294
Charles McCombie, Neil A. Chapman, Arius Association
(Switzerland); Tom Isaacs, LLNL/Stanford University (USA)
2. US EPAs Experiences Implementing Environmental Safety
Standards at the Waste Isolation Pilot Plant – 16103
Tom Peake, Chuck Byrum, Mike Eagle, Ed Feltcorn, Shankar
Ghose, Rajani Joglekar, US Environmental Protection Agency
(USA)
3. Repository Site Characterization - Learning from Experience –
16082
Martin Goldsworthy, Golder Associates (Germany); Till Popp,
IfG Institut für Gebirgsmechanik GmbH (Germany); Knut

Technical Sessions Tuesday PM
Seidel, GGL Geophysik und Geotechnik Leipzig GmbH
(Germany); Johannes Bruns, Golder Associates (Germany)
4. Amendments to the U.S. Environmental Protection Agencys
Public Health and Environmental Radiation Protection
Standards for Yucca Mountain, Nevada – 16156
Ray L. Clark, Ken Czyscinski, Reid J. Rosnick, Daniel
Schultheisz, US Environmental Protection Agency (USA)
—————— Break ——————
5. Experience with Technical Advisory Groups in the Japanese LW
Disposal Programme – 16290
Hiroyuki Tsuchi, Kazumi Kitayama, Akira Deguchi, Yoshiaki
Takahashi, Nuclear Waste Management Organization of Japan
(Japan); Toshiaki Ohe, Tokai University
(Japan): Charles McCombie, Arius Association (Switzerland);
Ian McKinley, McKinley Consulting (Switzerland)
6. Current Statue of Phase II Investigation, Mizunami
Underground Research Laboratory (MIU) Project – 16262
Tadahiko Tsuruta, Masahiro Uchida, Katsuhiro Hama, Hiroya
Matsui, Shinji Takeuchi, Kenji Amano, Ryuji Takeuchi,
Hiromitsu Saegusa, Toshiyuki Matsuoka, and Takashi Mizuno,
Japan Atomic Energy Agency (Japan)
7. Approaches for Modelling Transient Unsaturated-Saturated
Groundwater Flow During and After Construction – 16242
Matt White, Galson Sciences Limited (UK); Jordi Guimera,
AMPHOS XXI Consulting S.L (Spain); Hiroshi Kosaka, Takuya
Ohyama, Japan Atomic Energy Agency (Japan) Peter Robinson,
Quintessa Limited (UK) Hiromitsu Saegusa, Japan Atomic
Energy Agency (Japan)
8. Integrated Model of Korean Spent Fuel and High Level Waste
Disposal Options – 16091
Yongsoo Hwang, KAERI (Korea); Ian Miller, GoldSim
Technology Group (USA)
SESSION 29
Tuesday 13:45 Room 12
MODELING APPROACHES FOR HLW, SNF, AND TRU
WASTE DISPOSITION
Co-Chairs: James Marra, SRNL (USA)
Jeff Griffin, SRNL (USA)
Organizer: Murthy Devarakonda, Washington TRU Solutions
LLC (USA)
1. Development of the ENVI Simulator to Estimate Korean SNF
Flow and its Cost – 16060
Yongsoo Hwang, KAERI (Korea); Ian Miller, GoldSim
Technology Group (USA)
2. Integration of the H2 Inhibition Effect of UO 2 2 Matrix
Dissolution into Radiolytic Models – 16239
Lara Duro, Abel Tamayo, Jordi Bruno (Spain); Aurora
Martínez-Esparza, ENRESA (Spain)
3. Separation of Lanthanoid Phoshates from the Spent Electrolyte
of Pyroprocessing – 16265
Ippei Amamoto, Hirohide Kofuji, Munetaka Myochin, Japan
Atomic Energy Agency (Japan); Tatsuya Tsuzuki, Central Glass
Co.Ltd (Japan); Yasushi Takasaki, Akita University (Japan);
Tetsuji Yano, Tokyo Institute of Technology (Japan); Takayuki
Terai, <strong>The</strong> University of Tokyo (Japan)
4. Implementation of a Geological Disposal Facility (GDF) in the
UK by the NDA RWMD: Coupled Modelling of Gas Generation
and Multi-Phase Flow between the Co-Located ILW and
HLW/SF Components of a GDF – 16307
Alex Bond, George Towler, Alan Paulley, Quintessa Limited
(UK); Simon Norris, NDA RWMD (UK)
SESSION 30
Tuesday 16:15 Room: 12
SPENT FUEL, HLW, AND TRU WASTE MANAGEMENT -
CROSSCUTTING ISSUES
Co-Chairs: Andy Malkin, Dounreay (UK)
Vomvoris Stratis, NAGRA (SWITZERLAND)
Organizers: Andy Malkin, Vomvoris Stratis
1. <strong>The</strong> U.S. Department of Energy Office of Environmental
Management (DOE-EM) <strong>International</strong> Cooperative Program -
Efforts being Conducted under the Statement of Intent between
DOE-EM and U.K. Nuclear Decommissioning Authority (NDA)
and Future <strong>International</strong> Activities – 16338
Steven L. Krahn, Kurt D. Gerdes, Ana M. Han, U.S.
Department of Energy (USA); James Marra, SRNL (USA).
2. Implementation of a Geological Disposal Facility (GDF) in the
UK by the NDA RWMD: <strong>The</strong> Potential for Interaction between
the Co-Located ILW/LLW and HLW/SF Components of a GDF
– 16306
George Towler, Quintessa Limited (UK); Tim Hicks, Galson
Sciences Ltd (UK); Sarah Watson, Quintessa Limited (UK);
Simon Norris, NDA RWMD (UK)
3. <strong>The</strong> Role of the Savannah River National Laboratory as <strong>The</strong>
DOE Environmental Management Corporate Laboratory –
16175*
Samit Bhattacharyya, John Marra, Jeff Griffin, William
Wilmarth, Savannah River National Laboratory (USA)
4. Evolution of the Quality Assurance Program for TRU Waste
Repository Operations, Waste Characterization and
Transportation at the Waste Isolation Pilot Plant – 16152*
Ava L. Holland, Department of Energy (USA)
SESSION 31
Tuesday 13:45 Room:13
ER SITE CHARACTERIZATION AND MONITORING - PART
1 OF 2
Co-Chairs: Leo van Velzen, NGR (SWITZERLAND)
Virgene Mulligan, ARS <strong>International</strong> (USA)
Organizer: Virgene Mulligan
1. A Practical Approach to Characterise and Assess a Site Drainage
System in Support of Site Restoration – 16008
Angela Bartlett, UKAEA Harwell (UK); Gavin Coppins,
UKAEA (UK); Peter Burgess, Nuvia (UK)
2. Benefits of Low Resolution Gamma Spectroscopy (LRGS) in
Assessment and Remediation of Alpha Contamination – 16023
Martha McBarron, Aker Solutions (UK); Jim Cassidy, Fathoms
Ltd (UK); Louise Hutton, Low Level Waste Respository (UK)
3. Safe Management of Radioactive Materials found in Public
Locations – 16032
Andrew Lewcock, Safeguard <strong>International</strong> Solutions Ltd. (UK);
Colette Grundy, Catherine Shaw, Environment Agency (UK)
4. An Integrated System for Conducting Radiological Surveys of
Contaminated Sites – 16312
Charles Waggoner, Donna Rogers, Jay McCown, Mississippi
State University (USA)
—————— Break ——————
5. Interdigitated Electrode Array Based Sensors for Monitoring of
Caesium – 16123
Ian D Nickson, John Tyndall Institute for Nuclear Research
(UK); Colin Boxall, Lancaster University (UK); G. Garnham,
National Nuclear Laboratory (UK); Simon. N Port, DSTL (UK)
6. Cone Penentration Testing of Radiologically Contaminated
Burial Trenches – 16086
Gareth Walker, Matt Lennard, Jeremy Lightfoot, Golder
Associates (UK); Nick Jefferies, Serco Assurance (UK)
7. <strong>The</strong> Advanced Pegasus Overland Radiation Detection System –
16321
Jeffrey Lively, Alejandro Lopez, Michael Marcial, MACTEC
(USA); Mark Liddiard, Joe Toole, WorleyParsons (UK)
23

Tuesday PM Technical Sessions
8. <strong>The</strong> Effect of Shielding Geometries on Dose Rate Mapping
Using In-Situ Gamma Spectrometry and Dose Inferring
Software N-Visage (TM)
– 16130
Jamie Adams, Lancaster University (UK); Matthew Mellor,
React Engineering Ltd. (UK); Malcolm Joyce, Lancaster
University (UK)
SESSION 32
Tuesday 13:45 Room: 14
LOCAL PARTICIPATION AND DECISION-MAKING
PROCESSES, BEHAVIOR AND POLITICS
Co-Chairs: Nadja Zeleznik, ARAO (SOLVENIA)
Grant Koroll, AECL (CANADA)
Organizer: Jennifer Biedscheid, Washington Division of URS
(USA)
1. Threats and Benefits the Updated Information on Local
Opinions Regarding the Spent Nuclear Fuel Repository in
Finland – 16128
Matti Kojo, University of Tampere (Finland); Mika Kari, Tapio
Litmanen, University Jyväskylä (Finland)
2. Applying Best Practical Environmental Optioneering (BPEO) to
a Complex Clean Up Programme; A Ponds & Silos Case Study –
16154
Simon Candy, Sellafield Ltd. (UK)
3. Stakeholder Participation for the Legacy Ponds and Legacy
Silos (LP&LS) Facility at Sellafield, Cumbria. UK: <strong>The</strong> Nature
and Effectiveness of the Dialogue – 16030
John Whitton, UK National Nuclear Laboratory (UK)
4. Experience in Choices for Decommissioning the Dounreay Site
– 16183
Fred Catlow, Fred Catlow, Independent Nuclear Consultant
(UK)
SESSION 33
Tuesday 16:15 Room:14
DIALOGUE TECHNIQUES: DIALOGUE VERSUS
CONSULTATION, COMMUNICATION OF RISK,
EDUCATION, USE OF WEB TECHNOLOGY
Co-Chairs: Mark Wareing, NDA (UK)
Rolf Sjöblom, Tekedo AB (SWEDEN)
Organizer: Jennifer Biedscheid, Washington Division of URS
(USA)
1. Training Activities and Perspectives in the Radioactive Waste
Management Area of Moscow SIA “Radon” – 16131
Olga Batyukhnova, Scientific and Industrial Association
“Radon” (Russia); Arthur Arustamov, Natalia Arustamova,
Sergey Dmitriev, SUE SIA “Radon” (Russia); Michael Ojovan,
University of Sheffield (UK); Zoran Drace, <strong>International</strong> Atomic
Energy Agency (Austria)
2. Evaluating LILRW Repository Impacts Due to Technologic
Stigma – 16229
Mojca Golobic, Alenka Cof, University of Ljubljana (Slovenia);
Marko Polic, University of Ljubljana (Slovenia)
3. Radioactive Waste: Show Time? – 16309
Hans Codee, COVRA N.V., Ewoud Verhoef, COVRA
(Netherlands)
4. Experiences of Teaching Decommissioning – 16179
Fred Catlow, Independent Nuclear Consultant (UK)
24
SESSION 34
Tuesday 08:30 Room: 2nd Floor
POSTER SESSION
Co-Chairs: Ian Beadle, AMEC Nuclear UK Limited (UK)
David Wallace, CDM (USA)
Organizer: Ian Beadle, AMEC, (UK)
LOW/INTERMEDIATE LEVEL WASTE
A. <strong>The</strong> Rock Creep Evaluation in the Analysis System for the
Long-Term Behavior of TRU Waste Disposal System – 16110
Shintaro Ohno, Seiji Morikawa, Kajima Corporation (Japan);
Morihiro Mihara, Japan Atomic Energy Agency (Japan)
B. Comparison of Actinides Separation by Coprecipitation and
Actinide Chromatographic Resin (Dipex®) for Gross Alpha
Determination – 16249
Esperanza Lara, Marina Rodriguez, CIEMAT (Spain)
C. Novel Antimonysilicate Material Quasar-N for the Removal of
Radionuclides from Acidic Decontamination Liquids – 16157
Risto Harjula, Airi Paajanen, University of Helsinki (Finland)
D. Further Development of Iodine Immobilization Technique by
Low Temperature Vitrification with BiPbO2I – 16268
Atsushi Mukunoki, Tamotsu Chiba, JGC Corporation (Japan);
Yasuhiro Suzuki, JGC Corporation (Japan); Kenji Yamaguchi,
Tomofumi Sakuragi, Radioactive Waste Management Funding
and Research Center (Japan); Tokuro Nanba, Okayama
University (Japan)
E. Improvement of Institutional Radioactive Waste Management
Via the Implementation of the Environmental Management
System – 16094
Marija Fabjan, Agency for Radwaste Management (Slovenia);
Metka Kralj, Bojan Hertl, ARAO - Agency for Radwaste
Management (Slovenia); Jože Rojc, RŽV - Mine Žirovski
vrh (Slovenia)
F. <strong>The</strong> KNOO Research Consortium: Work Package 3 An
Integrated Approach to Waste Immobilisation and Management
– 16375
Simon Biggs, Michael Fairweather, James Young, University of
Leeds (UK); Robin Grimes, Imperial College London (UK); Neil
Milestone, University of Sheffield (UK): Francis Livens, <strong>The</strong>
University of Machester (UK)
G. Hydraulic Behaviour Of Nuclear Waste Flows – 16376
Simon Biggs, Michael Fairweather, David Harbottle, Bo Lin,
James Young, Jeff Peakall, University of Leeds (UK)
H. Engineering Properties of Nuclear Waste Slurries – 16378
Simon Biggs, Michael Fairweather, Tim Hunter, Qanita
Omokanye, Jeff Peakall, James Young, University of Leeds (UK)
I. Radioactive Waste Management in Kenya – 16366
Anthony Shadrack, Ministry of Health (Kenya)
J. <strong>The</strong> Complexation of Tc(IV) with Gluconic Acid at High pH –
16381*
Sneh Jain, Ricky Hallam, Peter Warwick, Nick Evans,
Loughborough University (UK)
K. Management of Metal Waste with High Concentration of
Natural Radionuclides, its Problems and Experience – 16222
Alexander B. Gelbutovskiy, JSC “ECOMET-S"(Russia) Peter I.
Cheremisin, Alexander V. Troshev, Ecomet-S (Russia)
L. Study of the Radioactive Silt Sediment Cementation Techniques
– 16138
Andrey Varlakov, Sergey Karlin, Aleksandr Barinov, Moscow
Scientific-Industrial Association Radon (Russia); Elena
Zaharova, Vycheslav Ermolaev, IPCE RAS (Russia)
M. 5000th Mosaik - Cask Delivered in 2007 - A Story of Success –
16216
Olaf Oldiges, GNS Gesellschaft fuer Nuklear (Germany)
N. Cementation of Problem LRW Using Porous Concrete – 16139
Andrey Varlakov, Aleksandr Germanov, Aleksandr Barinov,
Sergey Dmitriev, Moscow Scientific-Industrial Association
Radon (Russia); Arthur Arustamov, SUE SIA Radon(Russia)
O. Separation of Lanthanide Fission Products in a Eutectic Waste
Salts Delivered from Pyroprocessing of a Spent Oxide Fuel by
Using Lab-Scale Oxidative Precipitation Apparatus – 16127
Yung-Zun Cho, Korea Atomic Energy Research Institute (Korea)

Technical Sessions Wednesday AM
Wednesday, October 14, 2009
SESSION 35 - MERGED WITH #46
Wednesday AM
THIS PANEL HAS BEEN MERGED WITH PANEL SESSION 46
SESSION 36
Wednesday 08:30 Room: 3B
D&D TECHNOLOGIES - I
Co-Chairs: Maria Lindberg, Studsvik UK Ltd (UK)
Keith Anderson, ECC (USA)
Organizers: Detlef Schmidt, Keith Anderson
1. Options for the Removal of Contaminated Concrete from the
Bore of the Windscale Pile Chimney – 16083
Colin Campbell, Dr. Jeremy Hunt, Sellafield Limited (UK);
Stephen Hepworth, Sellafield Ltd (UK)
2. Decommissiong of Active Effluent Gantries - AWE Aldermaston
– 16099*
Graham Rogers, NSG Environmental Ltd (UK)
3. Verification Test of Clearance Automatic Laser Inspection
System for Surface Contamination Measurement – 16109
Michiya Sasaki, Haruyuki Ogino, Takeshi Ichiji, Takatoshi
Hattori, Central Research Institute of Electric Power Industry
(Japan)
4. Preliminary Study of Cryogenic Cutting Technology for
Dismantling Highly Activated Facilities – 16006
Sung-Kyun Kim, Korea Atomic Energy Reserach Institute
(Korea); Dong-Gyu Lee, Kune-Woo Lee, Korea Atomic Energy
Research Institute (Korea)
—————— Break ——————
5. <strong>The</strong> Abrasive Blasting Unit at JRC-Ispra – 16270
Georg Braehler, Philipp Welbers, NUKEM Technologies GmbH
(Germany); Gianfranco Brunetti, Diederik van Regenmortel,
Joint Research Centre (Italy); Mike Kelly, Nuvia Limited (UK)
6. Decommissioning of the A-1 NPP Long-Term Storage Facility –
16299
Jan Medved, VUJE, Inc. (Slovakia); Ladislav Vargovcik, ZTS
VVU KOSICE a.s. (Slovakia)
7. Use of Full Recovery Hydrolasing Equipment for Facility
Decommissioning – 16325
Scott Martin, Scott Adams, S.A.Robotics (USA)
8. Current Activities of AllDeco at Decommissioning of the A1
NPP – 16333*
Jan Rezbarik, Stanislav Sekely, Jaroslav Katrlik, Dusan
Majersky, All Deco s.r.o. (Slovakia)
SESSION 37
Wednesday 08:30 Room: 3A
D&D RADIOLOGICAL CHARACTERIZATION AND
MONITORING
Co-Chairs: Michele Laraia, IAEA (AUSTRIA)
Ernest Warnecke, BfS (GERMANY)
Organizer: Michiya Saski
1. Critical Evaluation on the Use of Non-Destructive Assay of
Nuclear Packages through Destructive Breakdown and
Inventory Recovery – 16081
Stephen Hepworth, Rob Way, Sellafield Ltd (UK); Johathan
Sharpe, VT Nuclear Services (UK)
2. Decommissioning of a Vitrification Facility: Rinsing Phase –
16231
Marielle Asou, CEA (France); Sebastien Leblanc, Fabrice
Bouchet, Franck Martin, AREVA (France)
3. <strong>The</strong> Level of Uncertainty in Materials Clearance – 16090
Peter Burgess, Nuvia (UK)
4. Environmental Remediation and Using a New Sorting and Free
Release System for Contaminated Soil at NPP A1 Site, Slovakia
– 16020
Ondrej Slavik, Miroslav Baca, Alojz Slaninka, VUJE, a.s.
(Slovakia); Stanislav Janecka, Camberra Packard (Slovakia);
Ján Sirota, JAVYS, a.s. (Slovakia)
—————— Break ——————
5. <strong>The</strong> Use of Radiological Characterisation in Support of the
Design and Build of a New Facility in an Area of Elevated Dose
Rate – 16009
Karl Hughes, David Thornley, VT Nuclear Services Ltd (UK);
Czeslaw Pienkowski, Sellafield Ltd. (UK)
6. <strong>The</strong> Application of Additional, Off-line, Analysis Techniques to
PCM Monitor Results to Aid the Efficient and Cost Effective
Repackaging of Legacy PCM Wastes Containing Plutonium
Fluoride – 16034
David Thornley, Kareena McCrindle, Stephen Rayner,
Jonathan Sharpe, VT Nuclear Services (UK); Czeslaw
Pienkowski, Carl Phillips, Sellafield Ltd (UK)
7. <strong>The</strong> Radioactivity Depth Analysis Tool (RADPAT) – 16144
Alan Shippen, Malcolm Joyce, Lancaster University (UK)
8. Remote Measurements of Radioactivity Distribution with
BROKK Robotic System – 16147
Oleg Ivanov, Alexey Danilovich, Vyacheslav Stepanov, Sergey
Smirnov, Victor Potapov, RRC Kurchatov Institute (Russia)
9. Radiological Characterisation throughout the UK Nuclear
Industry – 16300
Chris Hannon, Studsvik UK (UK)
SESSION 38
Wednesday 08:30 Room:11C
SITING, DESIGN, CONSTRUCTION, AND OPERATION OF
L/ILW DISPOSAL FACILITIES
Co-Chairs: Cathy Hickey, URS (USA)
Philip Rendell, NDA (UK)
Organizers: Cathy Hickey, Angie Jones, AMEC Earth &
Environmental (USA)
1. Design Options for the UKs ILW Geological Disposal Facility –
16241
Tim Hicks, Matt White, Tamara Baldwin, Paul Hooker, Phil
Richardson, Galson Sciences Ltd (UK); Neil Chapman,
Chapman & Co. Consulting (Switzerland); Fiona Neall, Neall
Consulting Ltd (UK); Ian McKinley, McKinley Consulting
(Switzerland); Samantha King, NDA RWMD, (UK)
2. Lessons Learned from the Operation of a L/ILW National
Disposal Centre: <strong>The</strong> Cabril and the Spanish Case – 16029
Emilio Garcia Neri, Mariano Navarro, Fernando Gomez,
ENRESA (Spain)
3. Hydrogeologic Modelling in Support of a Proposed Deep
Geologic Repository in Canada for Low and Intermediate Level
Radioactive Waste – 16264
Jonathan Sykes, Stefano Normani, Yong Yin, University of
Waterloo (Canada); Eric Sykes, Mark Jensen, Nuclear Waste
Management Organization (Canada)
4. I-Graphite Waste Management in France – 16301
Odile Ozanam, Gerald Ouzounian, ANDRA (France)
—————— Break ——————
5. Industrial Complex for Solid Radwaste Management (ICSRM)
at Chernobyl Nuclear Power Plant Functionality of the Facilities
- Experience of Project Execution – 16057
Heiko Eichhorn, NUKEM Technologies GmbH (Germany)
6. Experiences Related to the Development of a High Volume Very
Low Level Waste Disposal Facility in the UK – 16371
Andy Baker, Andy Baker Consulting Ltd (UK); Andrea Borwick,
WRG (UK); KayLin Loveland, Adam Meehan, Mike Travis,
EnergySolutions (UK); Ian Warner, Magnox North Ltd (UK)
7. Establishing a Site for a Slovenian L/ILW Repository – 16151
Sandi Viršek, Janja Ŝpiler, Miran Veselič, ARAO (Slovenia)
25

Wednesday AM Technical Sessions
SESSION 39
Wednesday 08:30 Room: 13
L/ILW WASTE HANDLING, TECHNOLOGIES, AND DATA
ANALYSIS (1 OF 3)
Co-Chairs: Ronald Keyser, ORTEC – AMETEK (USA)
Karan North, Magnox South Ltd (UK)
Organizer: Ronald Keyser
1. Improved Practices for Packaging Transuranic Waste at Los
Alamos National Laboratory (LA-UR 09-00333) – 16280
Kapil Goyal, Peter Carson, Los Alamos National Laboratory
(USA)
2. Radiological Assessment of Petroleum Pipe Scale Waste
Streams from Dry-Rattling Operations – 16323
Ian Hamilton, Foxfire Scientific, Inc. (USA); Robert Berry,
Matthew Arno, Erich Fruchtnicht, Foxfire Scientific (UK)
3. <strong>The</strong> DIAMOND University Research Consortium: Nuclear
Waste Characterisation, Immobilisation And Storage – 16374
Simon Biggs, Michael Fairweather, James Young, University of
Leeds (UK); Neil Hyatt, University of Sheffield (UK); Francis
Livens, <strong>The</strong> University of Machester (UK)
4. <strong>The</strong> Next EDF Tracking System – 16292
Emmanuelle Julli, Bertrand Lantes, EDF (France)
SESSION 40
Wednesday 10:45 Room: 13
L/ILW WASTE HANDLING, TECHNOLOGIES, AND DATA
ANALYSIS (2 OF 3)
Co-Chairs: Ronald Keyser, ORTEC – AMETEK (USA)
Karan North, Magnox South Ltd (UK)
Organizer: Ronald Keyser
1. Characterization of the Radiochemical Activity in Candu Steam
Generators – 16204
Aamir Husain, Yury Verzilov, Sriram Suryanarayan, Kinectrics,
Inc. (Canada)
2. Improved Algorithm for Close Geometry Characterization of
Waste Using Gamma-Ray Spectroscopy – 16320*
John Guo, Richard Hagenauer, ORTEC-AMETEK (USA);
Ronald Keyser, ORTEC – AMETEK (USA)
3. Field Examples of Waste Assay Solutions for Curium-
Contaminated Wastes – 16259
Patrick Chard, Canberra UK Ltd. (UK); Barrie Greenhalgh,
Sellafield Ltd. (UK); Ann Ross, Dounreay Site Restoration
Limited (DSRL) (UK); Tom Turner, UKAEA (UK); Ian
Hutchinson, Canberra UK Ltd (UK); Stephen Croft, Canberra
Industries Inc. (USA)
4. <strong>The</strong>oretical Modelling of Nuclear Waste Flows – 16377
J.F. Adams, S.R. Biggs, M. Fairweather, D. Njobuenwu and J.
Yao,University of Leeds (UK)
SESSION 41
Wednesday 08:30 Room: 4B
TRANSPORTATION AND STORAGE OF HLW, FISSILE, TRU,
AND SNF
Co-Chairs: Ed Bentz, E.J. Bentz & Associates (USA)
Phillip Gregory, Washington TRU Solutions (USA)
Organizer: Ed Bentz
1. Experience with Dry Cask Storage Technology in Germany –
16416
Heinz Geiser, Jens Schroeder, Dietrich Hoffmann, GNS mbH
(Germany)
2. Contingency Options for the Dry Storage of Magnox Spent Fuel
in the UK – 16330
Jenny E. Morris, Galson Sciences Limited (UK); Stephen
Wickham, Phil Richardson, Galson Sciences Ltd. (UK); Colin
Rhodes, NDA (UK); Mike Newland, UKAEA (UK)
3. WIPP: A Perspective From Ten Years of Operating Success –
16189
Phillip C. Gregory, Washington TRU Solutions (USA)
26
4. Research Reactor Spent Nuclear Fuel Shipment from the Czech
Republic to the Russian Federation – 16195
Frantisek Svitak, Karel Svoboda, Josef Podlaha, Nuclear
Research Institute Rez plc. (Czech Republic)
—————— Break ——————
5. <strong>The</strong>rmal Safety Analysis of a Dry Storage Cask for the Korean
Standard Spent Fuel – 16159
Jeong-Hun Cha, B. S. Youn, S. N. Kim, Kyunghee University
(Korea); K. W. Choi, Korea Institute of Nuclear Safety (Korea)
6. Contingency Options for the Drying, Conditioning and
Packaging of Magnox Spent Fuel in the UK – 16331
Jenny E. Morris, Phil Richardson, Stephen Wickham, Galson
Sciences Ltd. (UK); Colin Rhodes, NDA (UK); Mike Newland,
UKAEA (UK)
7. Nuclear Safety at the Heart of the Design of the New Sellafield
Product and Residue Store – 16077*
Alec Glover, Sellafield Limited (UK)
8. Engineering Challenges in the Mechanical Design of a New
Shielded Shipping Cask for Vitrified Waste Products – 16256
R.K. Gupta, S.P. Patil, D.S Sandhanshive, A.K. Singh, K.M.
Singh, Bhabha Atomic Research Centre (India)
SESSION 42
Wednesday 08:30 Room:12
ER SITE CHARACTERIZATION AND MONITORING - PART
2 OF 2
Co-Chairs: Virgene Mulligan, ARS <strong>International</strong> (USA)
Steven Brown, SENES (USA)
Organizer: Virgene Mulligan, ARS <strong>International</strong> (USA)
1. Radiological Characterization of a Copper/Cobalt Mining &
Milling Site – 16322
Matthew Arno, Janine Arno, Foxfire Scientific (USA); Donald
Halter, Foxfire Scientific, Inc. (USA); Robert Berry, Foxfire
Scientific, Inc.(UK); Stephen Gilliland, Noel Hamilton, Foxfire
Scientific (USA); Ian Hamilton, Foxfire Scientific, Inc. (USA)
2. Radioactivity in Surface and Groundwater Near Old Radium and
Uranium Mines in Portugal – 16258
Fernando P. Carvalho, Instituto Tecnológico e Nuclear
(Portugal); João M. Oliveira, Magarida Malta, Nuclear and
Technological Institute (Portugal)
SESSION 43
Wedneday: Directly After Session 42 Room: 12
URANIUM MINING AND MILLING SITES ER
Co-Chairs: Steven Brown, SENES (USA)
Peter Waggitt, IAEA (AUSTRIA)
Organizer: Steve Brown, SENES Consultants Ltd. (USA)
1. Design Improvements and ALARA at U.S. Uranium In Situ
Recovery Facilities – 16415
Steven Brown, SENES, Englewood (USA)
2. Radionuclide Transfer from Uranium Mine Water Treatment
Ponds to Vegetation – 16260
Fernando P. Carvalho, Instituto Tecnológico e Nuclear
(Portugal); João M. Oliveira, Magarida Malta, Nuclear and
Technological Institute (Portugal)
—————— Break ——————
3. Completion of the South Alligator Valley Remediation, Northern
Territory, Australia – 16198
Peter Waggitt, IAEA (Austria); Mike Fawcett, Fawcett Minesite
Rehabilitation Services (Australia)
4. Gunnar Uranium Mine Environmental Remediation - Northern
Saskatchewan – 16102
Joseph Muldoon, Laurier Schramm, Saskatchewan Research
Council (Canada)
5. Sustainable Covers for Uranium Mill Tailings, USA: Alternative
Design, Performance, and Renovation – 16369
William J. Waugh, S.M. Stoller Corporation (USA); Craig H.
Benson, University of Wisconsin-Madison (USA); William H.
Albright, Desert Research Institute (USA)

Technical Sessions Wednesday AM
SESSION 44
Wednesday 10:45 Room: 11B
PANEL: YOUNG GENERATION NETWORK (YGN)
Co-Chairs: Chris Williams, VT Nuclear Services (UK)
Robert Berry, Foxfire Scientific, Inc. (UK)
Organizers: Chris Williams, Robert Berry
This panel will focus on Young Generation Networks and Professional
Development. <strong>The</strong> panelists and topics will include Carl Dawson,
NDA National Graduate Program Manager and Craig Morrow (NDA
Graduate) on the creation and experiences of the Nuclear
Decommissioning Authority Graduate Scheme; Corhyn Parr (UK
YGN Vice Chair) presenting the results of a survey of UK YGN
members on attitudes and opinions of the UK Nuclear Industry and
Miguel Millan (President Spanish YGN) on the Development of the
Spanish YGN.
SESSION 45
Wednesday 08:30 Room: 2nd Floor
POSTER SESSION
Co-Chairs: Heather Klebba, Nuclear Filter Technologies(USA)
Terry Wickland, Nuclear Filter Technologies (USA)
Organizers: Don Goebel, SEC (USA); Jennifer Biedscheid,
Washington Division of URS (USA)
ENVIRONMENTAL REMEDIATION/EM POSTERS
A. New Uses for Natural Analogues - Determining Site Clean-Up
Criteria? – 16073*
Alison Robinson, University of Central Lancashire (UK)
B. Particle Detection - A New Mindset, MACTECs Detector
Research and Testing
Facility – 16284*
Alejandro Lopez, Michael Marcial, Michael McDonald, Jeffrey
Lively, MACTEC (USA)
C. Independent Monitoring of Radiological Impact in
Decommissioned NPP A1 Site – 16074
Ondrej Slavik, Martin Listjak, Alojz Slaninka, Jozef Moravek
(SlovaKia); Frantisek Soos, JAVYS, a.s. (Slovakia); Sylvia
Dulanska, Comenius University (Slovakia)
D. Experience of the <strong>International</strong> Cooperation under the Russian-
American Agreement on Repatriation HEU SNF of Research
Reactors (export from Bulgaria, Latvia, Hungary, etc. the
countries) – 16172
Borovitskiy Stepan, FSUE FCNRS (Russia)
E. Plan for Site Release of Decommissioning Project of KRR-1&2
– 16287*
Sang Bum Hong, Korea Atomic Energy Research Institute
(Korea)
F. Present State of Remediation of Mecsek Uranium Mines,
Radioactive Parameters – 16337*
András Várhegyi, MECSEK-ÖKO Environment Co. (Hungary);
Zorán Gorjánácz, MECSEKÉRC Environment Co. (Hungary);
János Somlai, Pannon University (Hungary)
SESSION 46
Wednesday 13:45 Room: 3A
PANEL: UK NDA AND TIER 1 FUNDING, CONTRACTING,
SUBCONTRACTING SELECTION AND ARRANGEMENTS
Co-Chairs: Richard Mrowicki, Nuclear Decommissioning
Authority (UK)
Fred Sheil, Sellafield Ltd. (UK)
Organizors: Richard Mrowicki, Fred Sheil
This workshop will summarize and provide a status report on funding,
contracting and the competition program for the NDA sites. <strong>The</strong> focus
will be to discuss openly with the audience experience, ideas and new
lessons that are applicable to the UK.
Panelists include: Mike Hawe, Commercial Director, Magnox North;
Keith Case, Commercial Director, Sellafield; David Savage, Program
Manager, Shared Services Alliance; Ron Gorham, Head of Supply
Chain Development, NDA; and Keith Gibson, Low Level Waste
Repository.
SESSION 47
Wednesday 13:45 Room:3B
PANEL: UMREG PANEL/ROUNDTABLE
Co-Chairs: Alex Jakubick, UMREG (AUSTRIA)
Steve Brown, SENES Consultants Ltd. (USA)
Organizer: Alex Jakubick
Panelists and topics include:
• Opening of the meeting. Activities of the past year.
Alex Jakubick, UMREG (Australia)
• US DOE’s Legacy Management Program: Implementation and
Experience
Jody Waug, S. M. Stoller Corp., US DOE Contractor (USA)
• Long Term Stewardship Program at the Wismut Legacy Sites,
Germany
Michael Paul, Wismut (Germany)
• Proposed Program for Long Term Monitoring and Maintenance
of Legacy Sites in Kazakhstan
Marat Kaftaranov, Uranlikvidrudnik (Kazakhstan)
• <strong>The</strong> Central Asian NATO Program and Status of the UNDP
Framework Document for Central Asia
Peter Stegnar, NATO Central Asian Program (Slovenia)
• Risks, Control and Monitoring of ISR. Does ISR Require a LTS
Program?
Steve Brown, SENES Consultants Ltd. (USA)
• Hydrogeological Monitoring Experience at the Hungarian
legacy Sites
Földig Gabor, MECSEK-ÖKO (Hungary)
• Developments in the Uranium Industry in Africa
Peter Waggitt, IAEA (Austria)
• Environmental and Clean-up Projects: An EBRD Perspective
Esther Harlander, EBRD (UK)
• Closure and Future Direction of UMREG
Alex Jakubick and Peter Waggitt
SESSION 48
Wednesday 13:45 Room:11C
LIQUID WASTE TREATMENT PROCESS AND EXPERIENCE
Co-Chairs: Paul Haigh, <strong>The</strong> Paul Haigh Partnership (UK)
Michael Ojovan, University of Selifield (UK)
Organizers: Alun Ellis, Radioactive WM Directorate (UK)
Angie Jones, AMEC Earth & Environmental, (USA)
1. U.S. Department of Energy’s “Initiatives for Proliferation
Prevention” Program: Solidification Technologies for
Radioactive Waste Treatment In Russia – 16037
Dennis Kelley, Pacific Nuclear Solutions (USA); Yury
Pokhitonov, V.G. Khlopin Radium Institute(Russia)
2. Operational Experience with a Commercial Plant for
Stabilisation of Radioactive Sludge and Other Materials in the
United Kingdom – 16042
Madoc Hagan, Rowland Cornell, Brian Riley, Nuvia Limited
(UK); Bryan Ware, UK Kingdom Atomic Energy Authority(UK)
3. <strong>The</strong> Development of a Method for the Simultaneous
Measurement of Cerium (IV) and Chromium (VI) Species in
Nitric Acid Media – 16124
Ian D Nickson, John Tyndall Institute for Nuclear Research
(UK); Colin Boxall, Lancaster University (UK); Angela
Jackson, Guy O.H. Whillock, National Nuclear Laboratory(UK)
4. Treatment of Liquid RAW - Trial Operation of Final Treatment
Center Mochovce – 16178*
Tibor Krajc, Milan Zatkulak, Marian Stubna, VUJE, a.s.
(Slovakia); Vladimir Remias, JAVYS, a.s., (Slovaki)
—————— Break ——————
5. Radioactive Oil Decontamination Development An Overview –
16251
John Krasznai, Kinectrics Inc. (Canada)
27

Wednesday PM Technical Sessions
6. Incineration of Contaminated Oil from Sellafield – 16246
Craig Broadbent, Studsvik UK Limited (UK); Helen Cassidy,
Sellafield Limited (UK); Anders Stenmark, Studsvik Nuclear AB
(Sweden)
7. Solidification of Radioactive Liquid Wastes, Treatment Options
for Spent Resins and Concentrates – 16405
Andreas Roth, Hansa Projekt Anlagentechnik GmbH (Germany)
8. <strong>The</strong> Sorption and Mechanical Properties of the Modified
Concrete Matrix Used for Conditioning of Radioactive Waste –
16255
Daniela Dogaru, National Commission for Nuclear Activities
Control (Romania); Ortenzia Niculae, National Agency for
Radioactive Waste (Romania); Gheorghita Jinescu, Politehnica
University of Bucharest (Romania); Octavian G. Duliu,
University of Bucharest (Romania); Gheorghe Dogaru, National
Institute of Reserch & Development for Physics and Nuclear
Engineering-Horia Hulubei (Romania)
SESSION 49
Wednesday 13:45 Room: 14
L/ILW WASTE ANALYSIS TECHNOLOGIES - PART 3 OF 3
Co-Chairs: Ronald Keyser, ORTEC – AMETEK (USA)
Karan North, Magnox South Ltd (UK)
Organizer: Ronald Keyser
1. Radiological Monitoring Systems for Waste Characterisation in
the Environment of our Decommissioning Solutions – 16013
Marina Sokcic-Kostic, Roland Schultheis, NUKEM
Technologies GmbH (Germany)
2. MGAv10: <strong>The</strong> Latest Evolution in the Multi-Group Analysis
Code – 16248
Stephen Croft, Andrey Bosko, Canberra Industries Inc. (USA;
Ray Gunnink, Consulant (USA); Sasha Philips, Joe
Lamontagne, Canberra Industries Inc. (USA); Markku Koskelo,
Canberra Albuquerque Inc. (USA); Robert McElroy, Canberra
Industries Inc. (USA)
3. Use of a Waste Tracking System as a Waste Management Tool –
16302*
Karan North, Magnox South Ltd (UK)
4. Design and Operation of the Combined Technology Automated
Waste Characterisation System – 16361
J. A. Mason, M. R. Looman, and R. Price, A. N. Technology
Ltd.(UK)
SESSION 50
Wednesday 16:15 Room:14
QUALITY ASSURANCE AND CONTROL IN RADIOACTIVE
WASTE MANAGEMENT
Co-Chairs: Jeroen Welbergen, COVRA (NETHERLANDS)
Bill Miller, AMEC, (UK)
Organizer: Angie Jones, AMEC Earth & Environmental, (USA)
1. Control of Materials Harmful to Water in the German KONRAD
Repository – 16125
Karin Kugel, Stefan Steyer, Peter Berneckee, Bundesamt fuer
Strahlenschutz (BfS (Germany); Detlef Gruendler, Wilma
Boetsch, Claudia Haider, ISTec GmbH (Germany)
2. Dose Validation in the Dutch Interim Waste Storage Facility –
16263
Jeroen Welbergen, Leo P.M. Van Velzen, Nuclear Research and
Consultancy Group (Switzerland)
3. Sorption Databases for Increasing Confidence in Performance
Assessment – 16053
Anke Richter, Vinzenz Brendler, Cordula Nebelung,
Forschungszentrum Dresden-Rossendorf e.V. (Germany);
Timothy E. Payne, Australian Nuclear Science and Technology
Organization (Australia); Thomas Brasser, GRS Braunschweig
(Germany)
4. Decommissioning and Waste Treatment Hazard Evaluation and
Modeling – 16409
Martin Plys, Michael Epstein, Fauske & Associates, LLC (USA)
28
SESSION 51
Wednesday 13:45 Room:4B
VITRIFICATION AND BOROSILICATE GLASS
ALTERNATIVES FOR IMMOBILIZATION
Co-Chairs: Pierre Van Iseghem, SCK•CEN (BELGIUM)
Carl Steele, Sellafield Ltd. (UK)
Organizers: Pierre Van Iseghem, Carl Steel
1. <strong>The</strong> Results of Testing to Evaluate Crystal Formation and
Settling in the Cold Crucible Induction Melter – 16282
James Marra, SRNL (USA); Sergey Stefanovsky, Dmitriy
Suntsov,Vladimir Lebedev, SIA Radon (Russia)
2. Cold Crucible Vitrification of SRS SB4 Waste at High Waste
Loadings – 16197
Sergey Stefanovsky, Alexander Kobelev, Vladimir Lebedev,
Michael Polkanov, Oleg Knyazev, SIA Radon (Russia); James
Marra, SRNL (USA)
3. On Fluidization of Borosilicate Glasses in Intense Radiation
Fields – 16055
Michael Ojovan, Guenter Möbus, Jim Tsai, Stuart Cook,
University of Sheffield (UK); Guang Yang, University of
Chicago (USA)
4. Design Innovations in Advanced Vitrification System at Tarapur
– 16254
Kalyan Banerjee, Rajendra Gupta, Sudhakaran Nair, Sridutt
Misra, Bhabha Atomic Research Centre (India)
—————— Break ——————
5. <strong>The</strong> Effect of Waste Loading on the Characteristics of
Borosilicate SRS SB4 Waste Glasses – 16196
Sergey Stefanovsky, Alexander Kobelev, Vladimir Lebedev,
Michael Polkanov, Dmitriy Suntsov, SIA Radon (Russia); James
Marra, SRNL (USA)
6. Diffusion of Helium in Borosilicate Glasses: A Comparative
Approach between Radioactive and Non-Radioactive Glasses –
16208*
Toby Fares, Sylvain Peuget, Atomic Energy Commission (CEA-
Marcoule) (France); Jacques Haussy, CEA (France); Xavier
Deschanels, ICSM (France)
7 Understanding Potential Release Mechanisms of Volatile
Ruthenium During the Vitrification of High Level Waste –
16288
Chris Brookes, Sellafield Ltd (UK); Yvonne Lawson, Mark
Sarsfield, National Nuclear Laboratory (UK); Carl Steele,
Sellafield Ltd. (UK)
SESSION 52
Wednesday 13:45 Room:12
A SYNOPSIS OF KNOWLEDGE MANAGEMENT SYSTEMS
Co-Chairs: Hiroyuki Umeki, Japan Atomic Energy Agency
(JAPAN)
Stuart Hunt, NDA (UK)
Organizer: Hiroyuki Umeki
1. Use of the Safety Case to Focus KMS Applications – 16348
Hideaki Osawa, Kazumasa Hioki, Hiroyuki Umeki, Japan
Atomic Energy Agency (Japan); Hiroyasu Takase, Quintessa
Japan, (Japan); Ian McKinley, McKinley Consulting
(Switzerland)
2. Practical Application of the KMS: 1) Total System Performance
Assessment – 16349
Hitoshi Makino, Kazumasa Hioki, Hiroyuki Umeki, Japan
Atomic Energy Agency (Japan); Hongzhi Yang, Hiroyasu
Takase, Quintessa Japan (Japan); Ian McKinley, McKinley
Consulting (Switzerland)
3. Practical Application of the KMS: 2) Site Characterization –
16355
Takeshi Semba, Hideaki Osawa, Kazumasa Hioki, Japan
Atomic Energy Agency (Japan); Shoko Tachibana, Hiroyasu
Takase, Quintessa Japan (Japan); Ian McKinley, McKinley
Consulting (Switzerland)

Technical Sessions Wednesday PM
4. Challenges for the JAEA KMS: Fostering Inventive Design and
Problem Solving – 16351
Hitoshi Makino, Kazumasa Hioki, Hiroyuki Umeki, Japan
Atomic Energy Agency (Japan); Shoko Tachibana, Hiroyasu
Takase, Quintessa Japan (Japan); Ian McKinley, McKinley
Consulting (Switzerland)
5. Overview of the JAEA KMS Knowledge Management System
Supporting Implementation and Regulation of Geological
Disposal in Japan – 16354
Hiroyuki Umeki, Kazumasa Hioki, Japan Atomic Energy
Agency (Japan); Hiroyasu Takase, Quintessa Japan (Japan);
Ian McKinley, McKinley Consulting (Switzerland)
SESSION 53
Wednesday 16:15 Room: 12
PANEL: FUTURE DIRECTION IN KNOWLEDGE
MANAGEMENT
Co-Chairs: Hiroyuki Umeki, Japan Atomic Energy Agency
(JAPAN)
Stuart Hunt, NDA (UK)
Organizers: Hiroyuki Umeki, Ian McKinley
This panel will consider the initiative instigated by JAEA in the
context of the common requirement to efficiently and rigorously
manage increasing large and complex fluxes of information produced
in all geological disposal programs. Emphasis will be on
distinguishing between program-specific constraints and more generic
areas, which could be a focus for future collaborative projects.
Panelists include: P. Marjatta Palmu, Posiva Oy, (FINDLAND);
Richard Shaw, British Geological Survey (BGS), (UK); Stuart
Hunt, Nuclear Decommissioning Authority, (UK); and Hiroyuki
Umeki, Japan Atomic Energy Agency, (JAPAN)
SESSION 54
Wednesday 13:45 Room:11B
D&D TECHNOLOGIES - PART 2
Co-Chairs: Christophe Le Goaller, CEA (FRANCE)
Maria Lindberg, Studsvik UK Ltd (UK)
Organizers: Christophe Le Goaller, Maria Lindberg
1. Advanced Radioactive Soil Screening and Sorting Technology –
16283
Jeffrey W. Lively, Michael R. Marcial, MACTEC (USA); Mark
Liddiard, Worley Parsons (UK); Javid Kelley, MACTEC (USA);
Joseph Toole, Worley Parsons (UK)
2. Fluorescence Spectral Imaging as a Tool for Locating Uranium
Deposited on Surfaces – 16089
David L. Monts, Institute for Clean Energy Technology (ICET)
(USA); Guangjun Wang, Yi Su, Ping-Rey Jang, Charles A.
Waggoner, ICET (USA)
3. Surface Decontamination by Photocatalysis – 16068
R. J. Wilbraham, C. Boxall, Lancaster University (UK): R. J.
Taylor, National Nuclear Laboratory (UK)
4. <strong>The</strong> Development of a Prototype of a Multi-Arm Robotic
System for Decontamination and Decommissioning (D&D)
Applications within the Nuclear Industry – 16017
Mohamed J. Bakari, Derek W. Seward, Taylor C. James,
Lancaster University (UK)
—————— Break ——————
5. A Review Of Vortex Amplifier Design in the Context of
Sellafield Nuclear Operations – 16063
Martin Birch, John Tyndall Institute of Nuclear Research (UK);
Raymond Doing, Sellafield Limited (UK); Johathan Francis,
University of Central Lancashire (UK); Darren Parker, Land
Securities Trillium (UK); Guobin Zhang, School of Electrical
and Electronic Engineering (UK)
6. Developments in the Long Term Preservation of Digital
Information for Nuclear Decommissioning – 16412
Jon Tilbury, Christina Tealdi, Tessella, (UK)
SESSION 55
Wednesday 13:45 Room:13
REGULATORY COMPLIANCE, RADIOLOGICAL SURVEYS,
AND FACILITY RELEASE
Co-Chairs: Simon Candy, Sellafield Ltd. (UK)
Axel Baecker, EWN, (BELGIUM)
Organizers: Simon Candy, Axel Baecker
1. Radiological, Technical and Financial Planning for
Decommissioning of Small Nuclear Facilities in Sweden –
16177
Rolf Sjöblom, Tekedo AB (Sweden); Staffan Lindskog, Swedish
Radiation Safety Authority (Sweden)
2. MARSAME: Multi-Agency Radiation Survey and Assessment
of Materials and Equipment – 16181
Kathryn Snead, Nidal Azzam, U.S. Environmental Protection
Agency (USA); Colleen F. Petullo, U.S. Public Health Service
(USA); Ramachandra Bhat, Craig Bias, U.S. Air Force (USA);
David P. Alberth, Gerald Falo, U.S. Army, Aberdeen Proving
Ground (USA); Steven Doremus, U.S. Navy, Yorktown (USA); W.
Alexander Williams, Amanda Anderson, U.S. Department of
Energy (USA); Robert A. Meck, George E. Powers, U.S. Nuclear
Regulatory Commission (USA)
3. Determination of the Radionuclide Inventory of Samples from a
Spallation Neutron Source – 16225*
Dorothea Schumann, Paul Scherrer Institute (Switzerland)
4. Measurement of Radioactive Aerosol Behavior during
Dismantling and Reflection to the Exposure Dose Evaluation –
16107
Yukihiro Iguchi, Masami Kato, Japan Nuclear Energy Safety
Organization (Japan)
—————— Break ——————
5. IAEA Decommissioning Safety Activities – 16397
Vladan Ljubenov, Ernst Warnecke, Mark Hannan, <strong>International</strong>
Atomic Energy Agency (Austria)
6. Plasma ARC Cutting Experiments using Radioactive Materials
for Evaluation of Airborne Dispersion Ratio – 16106
Taro Shimada, Japan Atomic Energy Agency (Japan); Atsushi
Takamura, Science System Laboratory (Japan); Atsushi Kamiya,
Nihon Advanced Technology (Japan); Takenori Sukegawa,
Tadao Tanaka, Japan Atomic Energy Agency (Japan)
7. <strong>The</strong> Development and Efficacy of the Continued Operations
Safety Report – 16067
Jonathan Francis, University of Central Lancashire (UK);
Gavin Smith, Sellafield Limited (UK); Ian D Nickson, John
Tyndall Institute for Nuclear Research (UK)
8. Planning for Decommissioning of an Irradiation Facility used
for Research Purposes in Cuba – 16120
Juan Carlos Benitez-Navarro, Mercedes Salgado-Mojena,
CPHR (Cuba); Evelio Soto Alvarez, Daniel Fraga Acosta,
CENSA (Cuba); Jose Quevedo, Yolanda Perez, CNSN (Cuba)
SESSION 56
Wednesday 13:30 Room: 2nd Floor
PROJECTS IN PROGRESS: NON-PAPER POSTER
Co-Chairs: Gary Benda, <strong>Conference</strong> Manager (USA)
Organizer: Gary Benda
This Poster Session is for presentations received after the acceptance
deadline and where a paper is not required.
1. Real System Analyses of PA Relevant Processes in Sediments:
<strong>The</strong> Ruprechtov Natural Analogue Site – 16342*
Vaclava Havlova, Nuclear Research Institute Rez plc.(Czech
Republic); Ulrich Noseck, Gesellschaft für Anlagen- und
Reaktorsicherheit (GRS) mbH (Germany); Melissa Denecke,
Wolfgang Hauser, FZK INE (Germany), Juhani Suksi, Helsinki
University (Findland); Kazimierz Rozanski, AGH (Poland)
2. A Truly Industrial Solution for the Elimination of Radioactive
Contaminated Oils or Solvents – 16232
Albert Jacobs, William Everett, Dewdrops (UK)
29

Thursday AM Technical Sessions
Thursday, October 15, 2009
SESSION 57
Thursday 08:30 Room:3B
D&D OF NON-REACTOR NUCLEAR FACILITIES
Co-Chairs: Jean-Marie Cuchet, Belgonucleaire (BELGIUM)
Neil Robson, Sellafield Ltd (UK)
Organizers: Jean-Marie Cuchet, Neil Robson
1. Progress and Experiences from the Decommissioning of the
Eurochemic Reprocessing Plant – 16022
Robert Walthery, Wim Van Laer, Patrick Lewandowski, Nancy
Reusen, Bart Ooms, Belgoprocess (Belgium)
2. Decommissioning of Buildings 105X and 122X at Belgoprocess
– 16052
Bart Ooms, Robert Walthery, Bert Lievens, Wim Van Laer,
Belgoprocess (Belgium)
3. Cleansing and Dismantling of CEA-Saclay Nuclear Licensed
Facilities – 16047
Michel Jeanjacques, Rebecca Glévarec, Isabelle Tirel,
Commissariat à l’Energie Atomique (France)
4. Decommissioning of High Hazard Legacy Facilities:
Comparison of Approaches in the Nuclear and Chemical Sectors
– 16084
Trevor Jones, Nuvia Limited (UK); Des Kelly, E4 Industry (UK)
—————— Break ——————
5. Challenges During the Decommissioning of the WAK Site -
Dismantling of Highly Contaminated HLLW-Storage Tanks –
16054
Joachim Dux, Oliver Fath, Belgium)WAK Rückbau- und
Entsorgungs-GmbH (Germany)
6. Uranium Workshops Decommissioning – 16219
Pierre Lisbonne, CEA (France)
7. Feasibility Study into the Application of Aggressive
Decontamination Techniques in Support of Reprocessing Plant
Decommissioning – 16079
Heather Moore, Sellafield Limited (UK); Stephen Hepworth,
Sellafield Ltd (UK)
8. Decommissioning of AECL Whiteshell Laboratories – 16311
Grant Koroll, Randall Swartz, Jeffrey Harding, AECL (Canada);
Michael Rhodes, McAlpine Enterprises (Canada); Randall
Ridgway, Dennis Bilinsky, AECL, Pinawa (Canada)
SESSION 58
Thursday 08:30 Room:12
D&D MANAGEMENT APPROACHES AND PLANNING
TOOLS
Co-Chairs: Ian Wheeler, Sellafield Ltd (UK)
Mark Denton, Kurion, Inc., Oak Ridge, TN, (USA)
Organizers: Ian Wheeler, Mark Denton
1. NEC3 - Managing Change – 16380
Charles Wilsoncroft, Hill <strong>International</strong> (UK)
2. A Successful Transition from Operating to Dismantling a UO2-
PuO2 Fuel Fabrication Facility – 16058
Thierry Flament, Jean-Louis Lemarchand, Marc Dalmier,
Dominique Pecquais, AREVA NC (France)
3. Tailoring Engineering Activities to D&D Projects – 16056
Charles Negin, Project Enhancement Corp.(USA); Andrew
Szilagyi, Yvette Collazo, U.S. Department of Energy (USA);
Charles Urland, Project Enhancement Corp. (USA); John
Gladden, Joe Santos, Savannah River National Laboratory
(USA)
4. Data Tracking System for Standardised Decommissioning
Costing – 16191
Vladimir Daniska, Ivan Rehak, Peter Bezak, Frantisek Ondra,
Marek Vasko, Decom, a.s. (Slovakia); Vladimir Necas, Slovak
University of Technology (Slovakia)
—————— Break ——————
5. Pet Cyclotron Design for Decommissioning and Waste
Inventory Reduction – 16098
Robert Major, AMEC (UK)
30
3. A Systematic Planning Tool for Environmental Characterisation
– 16010
Steven Wilcox, Richard I Wilkins, Martin R Lyons, AMEC (UK)
SESSION 59
Thursday 10:45 Room: 11B
SAFETY CONSIDERATIONS ASSOCIATED WITH L/ILW
MANAGEMENT
Co-Chairs: Ian Crossland, Crossland Consulting (UK)
Stephen Wickham, Galson Sciences Ltd (UK)
Organizers: Ian Corssland, Stephen Wickham
1. Development of Joint Regulatory Guidance on the Management
of Higher Activity Radioactive Wastes on Nuclear Licensed
Sites – 16095
Michael Bacon, Health and Safety Executive (UK); Doug Ilett,
Environment Agency (UK); Andrew Whittall, Scottish
Environment Protection Agency (UK)
2. Monte Carlo Simulation of a Compartment Model of
Radionuclide Migration at a Radioactive Waste Repository –
16168
Enrico Zio, Francesco Cadini, Diana Avram, Tommaso Girotti,
Politecnico (Italy); Alfredo Luce, ENEA CR Saluggia (Italy);
Alberto Taglioni, ENEA (Italy)
3. Preliminary Waste Acceptance Critera for LILW repository in
Slovenia – 16115
Nadja Zeleznik, ARAO (Slovenia); Dejan Skanata, Enconet
<strong>International</strong> (Croatia)
4. Safety Evaluation for Regulatory Management of Australian
Waste Operations Facilities – 16236
Samir Sarkar, Australian Radiation Protection and Nuclear
Safety Agency (Australia)
SESSION 60
Thursday 08:30 Room: 11C
L/ILW TREATMENT TECHNOLOGY DEVELOPMENT AND
IMPLEMENTATION
Co-Chairs: Keith Anderson, ECC (USA)
Ewoud Verhoef, COVRA (NETHERLANDS)
Organizers: Keith Anderson, Hans Codee
1. A New Approach to the Combined Conditioning of Solid and
Sludge Nuclear Waste – 16218
Lisa Hayes, Doug Kirk, BNES Nuclear Services (UK)
2. Experience with Operation of Movable Cementation Facility at
A1 NPP – 16038
Zuzana Holicka, Dusan Kevicky, Tibor Krajcl, Marian
Urbanec, VUJE, Inc. (Slovakia)
3. Construction and Operation of a Microfiltration Plant for the
Treatment of Radioactive Wastewater – 16019
Andreas Vesely, Herbert Trombitas; Nuclear Engineering
Seibersdorf (Austria)
4. NDA Generic Research Programme for Higher Activity Waste
Management Issues – 16390
James McKinney, Nuclear Decommissioning Authority (UK)
—————— Break ——————
5. Side Radwaste Treatment Facilities for the Westinghouse
AP1000 Projects in Sanmen und Haiyang, PR China – 16410
Andreas Roth, Hansa Projekt Anlagentechnik GmbH
(Germany); John Merrell, Westinghouse Electric Co Uk Ltd
(UK)
6. Statistical Modelling Applied to the Contents of Waste Drums –
16085
Richard Bull, Ian Pearman, Nuvia Limited (UK)
7. Study of the Radioactive Liquid Waste Treatment by
Coprecipitation: from Modelling to New Process Designs –
16018
Barré Yves, Pacary Vincent, Atomic Energy Commission
(France)
8. Trials of Experimental Module for Removal of Radioactive
Slurry from LRW Storage Tanks – 16238
Vadim A. Ilin, Moscow SIA “Radon” (Russia)(France)

Technical Sessions Thursday AM
SESSION 61
Thursday 08:30 Room:13
CHARACTERIZATION AND PERFORMANCE ASSESSMENT
FOR HLW, FISSILE, TRU, AND SNF
Co-Chairs: Hans Codee, COVRA N.V. (NETHERLANDS)
Phillip C. Gregory, Washington TRU Solutions (USA)
Organizers: Murthy Devarakonda, Washington TRU Solutions;
Gerry McGill, AMEC (UK)
1. Developing Design Premises for a KBS-3V Repository Based
on Results from the Safety Assessment – 16027
Johan Andersson, JA Streamflow AB (Sweden); Allan Hedin,
SKB (Sweden)
2. Characterization of a Fe- Based Alloy System for a GNEP
Metallic Wasteform – 16134
Mark Williamson, Savannah River National Lab (USA); Marie
Kane, Savannah River National Laboratory (USA); Bob
Sindelar, Savannah River National Lab (USA)
3. <strong>The</strong> Collaborative EC Project ReCosy – 16203
Bernhard Kienzler, Gunnar Buckau, Forschungszentrum
Karlsruhe (Germany)
4. Modelling Radionuclide Mobility of Spent Fuel in a Deep
Geological Repository Located in a Clay Bedrock – 16240
Abel Tamayo, Lara Duro, Jordi Bruno, Amphos 21 (Spain);
Aurora Martínez-Esparza, ENRESA (Spain)
—————— Break ——————
5. Evaluation of Mechanical Effects of the Fault Movement on the
Engineered Barrier System – 16269
Yuya Saito, Japan Atomic Energy Agency, (Japan); Mayuka
Nishimura, Takashi Hirai, Takenaka Civil Engineering &
Construction Co., Ltd, (Japan); Kenji Tanai, Morimasa Naito,
Japan Atomic Energy Agency (Japan)
6. Study on Performance Assessment for HLW Repository in China
– 16228
Weiming Chen, Ju Wang, Rui Su, Yunfeng Li, Beijing Research
Institute of Uranium Geology (China)
SESSION 62
Thursday 08:30 Room:4B
RECENT DEVELOPMENTS IN ER TECHNOLOGIES
Co-Chairs: Leo van Velzen, NRG (SWITZERLAND)
Virgene Mulligan, ARS <strong>International</strong> (USA)
Organizer: Leo van Vezen
1. <strong>The</strong> Development of Metallised Membranes for Analytical
Separation Processes – 16069
Michael A. Bromley, John Tyndall Institute for Nuclear
Research (UK); Colin Boxall, University of Lancaster (UK);
Sarah Galea, John Tyndall Institute for Nuclear Research (UK);
Jonathan Francis, University of Central Lancashire (UK)
2. Characterization of Cadmium-Resistant Bacteria and their
Application for Cadmium Bioremediation – 16072
Surasak Siripornadulsil, Wilailak Siripornadulsil, Khon Kaen
University (Thailand)
3. Enhanced Bioremediation as a Cost Effective Approach
following <strong>The</strong>rmally Enhanced Soil Extraction for Sites
Requiring Remediation of Chlorinated Solvents – 16296
Anna-Maria Kozlowska, AIG Engineering Group Limited (UK);
Steve R. Langford, AIG Engineering Group Limited (UK); Dr
H.G. Williams, EnviroGene Ltd (UK)
4. Bioavailability of Mercury in Contaminated Oak Ridge
Watershed and Potential Remediation of River/Runoff/Storm
Water by an Aquatic Plant – 16319
Yi Su, Fengxiang X. Han, Jian Chen, Yunju Xia, David L. Monts,
Mississippi State University (USA)
—————— Break ——————
5. Remediation of Uranium- and CHC-Contaminated Groundwater
on a Former Nuclear Fuel-Element Production Site – 16244
Joerg Woerner, Sonja Margraf, RD Hanau (Germany)
6. Polyphosphate Amendments for In-Situ Remediation of
Uranium – 16026
Dawn Wellman, Eric Pierce, Chase Bovaird, Pacific Northwest
National Laboratory (USA); John Bargar, Sam Webb, SSRL
(USA); Vince Vermeul, John Fruchter, Pacific Northwest
National Laboratory (USA)
SESSION 63
Thursday 08:30 Room:14
NATURAL ANALOGUES IN RADWASTE DISPOSAL -
ANSWERING THE HARD QUESTIONS
Co-Chairs: W. Russell Alexander, Bedrock Geosciences
(SWITZERLAND)
Tony Milodowski, British Geological Survey (UK)
Organizer: W. Russell Alexander
1. Implications of Microbial Redox Catalysis in Analogue Systems
for Repository Safety Cases – 16336
Julia M West, British Geological Survey (UK); Ian McKinley,
McKinley Consulting (Switzerland); Simcha Stroes-Gascoyne,
2. AECL, Whiteshell Laboratories (Canada)
Altered Crystalline Rock Distributed Along Groundwater
Conductive Fractures and the Retardation Capacity in the
Orogenic Field of Japan -16332
Yoshida Hidekazu, Nishimoto Shoji, Nagoya University
(Japan); Richard Metacalfe, Quintessa, Oxfordshire (UK)
3. Geochemical Behaviour of Uranium in Sedimentary Formations:
Insights from a Natural Analogue Study – 16340
Ulrich Noseck, Gesellschaft für Anlagen- und Reaktorsicherheit
(GRS) mb (Germany); Juhani Suksi, Helsinki University
(Finland); Vaclava Havlova, Radek Cervinka, Nuclear Research
Institute Rez plc. (Czech Republic); Thomas Brasser, GRS
Braunschweig (Germany)
4. <strong>The</strong> Ruprechtov Natural Analogue Site (CZ) Study: Mobile
Natural Organic Matter Idenification, Characterization and Link
to PA Relevant Processes – 16341
Vaclava Havlova, Nuclear Research Institute Rez plc. (Czech
Republic); Ulrich Noseck, Gesellschaft für Anlagen- und
Reaktorsicherheit (GRS) mbH (Germany); Radek Cervinka,
Nuclear Research Institute Rez plc. (Czech Republic); Thomas
Brasser, GRS Braunschweig (Germany); Josef Havel, Masaryk
University (Czech Republic)
—————— Break ——————
5. <strong>The</strong> Archaeological Analogue Approaches to Predict the Long
Term Corrosion Behaviour of Carbon Steel Overpack and
Reinforced Concrete Structures in the French Disposal Systems
– 16343
Delphine Neff, CEA (France); Mandana Saheb, CEA/ANDRA
(France); Judith Monnier, CNRS (France); Solenn REGUER,
Synchrotron SOLEIL (France); Walter Chitty, AREVA (France);
Stéphane Perrin, Michael Descostes, Valérie L’Hostis, CEA
(France); Didier Crusset, ANDRA (France); Philippe
Dillmann, CNRS (France)
6. Formation of Secondary Minerals and Uptake of Various Anions
Under Naturally-Occurring Hyperalkaline Conditions in Oman -
16344
Sohtaro Anraku, Tsukuba Sato, Tetsuro Yoneda, Hokkaido
University (Japan); Kazuya MORIMOTO, National Institute for
Materials Science (Japan)
7. Reaction of Bentonite in Low Alkali Cement Leachates:
Preliminary Results from the Cyprus Natural Analogue Project
(CNAP) – 16276
W. Russell Alexander, Bedrock Geosciences (Switzerland)
8. Developments in Hyperalkaline Natural Analogue
Studiesaround the Zambales Ophiolite, Philippines - 16278
C. Pascua, M. L.L. Honrado, University of Philippines
(Philippines); W. Russell Alexander, Bedrock Geosciences
(Switzerland); Yamakawa, N. Fujii, RWMC (Japan); K. Namiki,
K. Kawamurs, Obayashi Corpration (Japan); I.G. McKinley,
McKinley Consulting (Switzerland)
31

32
Exhibition Hours and Exhibitor Floorplan
Sunday, October 11, 2009 18:00 - 20:00
Monday, October 12, 2009 07:30 - 18:00
Tuesday, October 13, 2009 07:30 - 19:30
Wednesday, October 14, 2009 07:30 - 16:30

Exhibitors Listings
We would like to thank all of our exhibiting companies.
Company descriptions and contact information is listed in the next section, along with our Sponsors ads.
Exhibitors in Alphabetical Order
STAND COMPANY
48 AMEC (Gold Sponsor)
21 A. N. TECHNOLOGY LTD
8 AREVA
7 ASEM, IMECHE & INFORMATION POINT
15 ASSYSTEM ENERGY & NUCLEAR
(Bronze Sponsor)
32 ATKINS
40 ATTENTIONIT LTD
36 AUGEAN PLC
28 BELGOPROCESS
50 BNS NUCLEAR SERVICES (Platinum Sponsor)
CH2M Hill (Silver Sponsor - Sponsor Only)
6 CVD NUCLEAR SOLUTIONS
55 DAHER
45 DEWDROPS (Bronze Sponsor)
5 DIAMND DECTORS LTD.
2 DOOSAN BABCOCK ENERGY LIMITED
41 ENERGYSOLUTIONS (Silver Sponsor)
26 GNS GESELLSCHAFT FÜR
NUKLEAR- SERVICE
58 GOLDSIM TECHNOLOGY GROUP
1 GRAVATOM
11 GREIF UK LTD
42 HALLIN ROBOTICS LIMITED
7 IMECHE & INFORMATION POINT
69 INTERNATIONAL NUCLEAR SERVICES
71 INUTEC (formerly WMT LTD)
67 JFIMS & JFN
68 JORDAN NUCLEAR
74 LLW REPOSITORY LTD.
10 LOKRING TECHNOLOGY LLC
38 MECH-TOOL ENGINEERING LTD
25 NAC INTERNATIONAL
46 NATIONAL NUCLEAR LABORATORY (NNL)
(Silver Sponsor)
13 NI
39 NIA
53 NIS LTD
52 NSG ENVIRONMENTAL LTD (Silver Sponsor)
59 NUCLEAR FILTER TECHNOLOGY
23 NUCLEAR TECHNOLOGIES
24 NUKEM TECHNOLOGIES GmbH
43 NUVIA LIMITED (Silver Sponsor)
31 ORTEC
20 OXFORD TECHNOLOGIES LTD
73 PACTEC, INC. (Bronze Sponsor)
19 PAR SYSTEMS, INC.
62 PROJECT TIME & COST UK, LTD/PROJECT
TIME & COST, INC.
54 REMEDI8
22 S.A. ROBOTICS LTD
65 SELLAFIELD LTD
34 STUDSVIK
30 TESSELLA
33 UKAEA
37 UNITECH SERVICES GROUP
60 URS CORPORATION (Platinum Sponsor)
18 VENN ENGINEERING SERVICES LTD
3 VT GROUP (Silver Sponsor)
14 YGN - YOUNG GENORATION NETWORK
63 WESTINGHOUSE ELECTRIC COMPANY
(Silver Sponsor)
56 WORLEYPARSONS
Exhibitors in Numerical Order
STAND COMPANY
1 GRAVATOM
2 DOOSAN BABCOCK ENERGY LIMITED
3/4 VT GROUP (Silver Sponsor)
5 DIAMOND DETECTORS LTD
6 CVD NUCLEAR SOLUTIONS
7 ASEM, IMECHE & INFORMATION POINT
8/9/16/17 AREVA
10 LOKRING TECHNOLOGY LLC
11/12 GREIF UK LTD
13 NI
14 YGN - YOUNG GENORATION NETWORK
15 ASSYSTEM ENERGY & NUCLEAR
(Bronze Sponsor)
18 VENN ENGINEERING SERVICES LTD
19 PAR SYSTEMS, INC.
20 OXFORD TECHNOLOGIES LTD
21 A. N. TECHNOLOGY LTD
22 S.A. ROBOTICS LTD
23 NUCLEAR TECHNOLOGIES
24/27 NUKEM TECHNOLOGIES GmbH
25 NAC INTERNATIONAL
26/29 GNS GESELLSCHAFT FÜR NUKLEAR-
SERVICE
28 BELGOPROCESS
30 TESSELLA
31 ORTEC
32 ATKINS
33 UKAEA
34/35 STUDSVIK
36 AUGEAN PLC
37 UNITECH SERVICES GROUP
38 MECH-TOOL ENGINEERING LTD
39 NIA
40 ATTENTIONIT LTD
41 ENERGYSOLUTIONS (Silver Sponsor)
42 HALLIN ROBOTICS LIMITED
43/44 NUVIA LIMITED (Silver Sponsor)
45 DEWDROPS (Bronze Sponsor)
46/47 NATIONAL NUCLEAR LABORATORY
(NNL) (Silver Sponsor)
48/49 AMEC (Gold Sponsor)
50/51/83/84 BNS NUCLEAR SERVICES
(Platinum Sponsor)
52 NSG ENVIRONMENTAL LTD
(Silver Sponsor)
53 NIS LTD
54 REMEDI8
55 DAHER
56/57 WORLEYPARSONS
58 GOLDSIM TECHNOLOGY GROUP
59 NUCLEAR FILTER TECHNOLOGY
60/61 URS CORPORATION (Platinum Sponsor)
62 PROJECT TIME & COST INC/UK LTD
63/64 WESTINGHOUSE ELECTRIC COMPANY
(Silver Sponsor)
65/66 SELLAFIELD LTD
67 JFIMS & JFN
68 JORDAN NUCLEAR
69/70 INTERNATIONAL NUCLEAR SERVICES
(INS)
71/72 INUTEC (formerly WMT LTD)
73 PACTEC, INC. (Bronze Sponsor)
74/75 LLW REPOSITORY LTD
33

AMEC STAND: 48/49
GOLD SPONSOR
Contact: Tony Lawrence
601 Faraday Street, Birchwood, Warrington,
Cheshire, WA3 6QN
UNITED KINGDOM
Tel: +44 (0)1925 675000
Email: anthony.lawrence@amec.com
www.amec.com
AMEC has experience of decommissioning in the UK, Canada,
Eastern and Western Europe, Lithuania, Ukraine, Armenia and
Russia. We offer a complete range of nuclear services that span
the full life-cycle of any decommissioning project, from
developing the initial concept through to hands-on
decommissioning and clean-up.
With our safety, health physics and environmental support we
act as a single supplier, delivering the full range of skills and
services for the completion of any decommissioning project;
managing the decontamination and decommissioning of
facilities to minimise the environmental impact and pave the
way for site regeneration.
We have acknowledged experts in waste management, health
physics and all radiological and environmental services to
include, RPA, waste characterisation and management,
dosimetry, monitoring, analysis and subsequent clean-up. We
have waste characterisation experience using on-site gamma
spectrometry measurement and analysis via NIRAS
Laboratories.
AMEC also provides all levels of nuclear safety case, design
substantiation and ALARP/BPEO justification, including
regulatory support. <strong>The</strong> radiological capability includes
analysis and modelling; criticality and shielding assessments,
and the application of thermohydraulic and radiological
analysis codes.
Our commitment to safe and efficient on-site operations
demand highly skilled and innovative project management, and
our project teams focus on ensuring that our customers’
requirements are met.
A. N. TECHNOLOGY LTD STAND: 21
Contacts: Units 5/6 Thames Park
Lester Way
Wallingford
Oxfordshire, OX10 9TA
UNITED KINGDOM
Tel: +44 01491 824444
www.antech-inc.com
For more than 20 years ANTECH have produced a range of
nuclear instrumentation solutions for the measurement and
characterisation of SNM and radionuclides in waste and
provide sales, service and support worldwide.
Our products are used to measure waste in crates, boxes, drums
and cans and fall into three basic categories or combinations
thereof:
• Gamma Ray Measurement Systems
• Neutron Measuring Measurement Systems
• Calorimeter Measurement Systems
• Combined Technology Systems and Instruments
• including Portal Monitoring for Homeland Security
• Custom Systems
<strong>The</strong> Company also provides fully automated waste
characterisation systems employing multiple technologies,
conveyors and drum handling equipment.
AREVA STAND: 8
Contact: www.areva.com
All over the world, AREVA provides its customers with
solutions for carbon-free power generation and electricity
transmission. With its knowledge and expertise in these fields,
the group has a leading role to play in meeting the world’s
energy needs.
Ranked first in the global nuclear power industry, AREVA’s
unique integrated offering covers every stage of the fuel cycle,
reactor design and construction, and related services.
In addition, the group is developing a portfolio of operations in
renewable energies. AREVA is also a world leader in electricity
transmission and distribution and offers its customers a
complete range of solutions for greater grid stability and
energy efficiency.
Sustainable development is a core component of the group’s
industrial strategy. Its 75,000 employees work every day to
make AREVA a responsible industrial player that is helping to
supply ever cleaner, safer and more economical energy to the
greatest number of people.
ASSYSTEM STAND: 15
ENERGY & NUCLEAR
BRONZE SPONSOR
Contact: Derek Williams, Sales Director
Club Street
Bamber Bridge
Preston PR5-6FN
UNITED KINGDOM
Tel: +44 ( 0)1772 645 000
email: dwilliams@assystemuk.com
www.assytem.com
<strong>The</strong> ASSYSTEM Group is one of Europe’s leading Engineering
Services providers with a total turnover of £650m and
employing over 9500 staff at its offices throughout France, the
UK and worldwide. Since it originated in the Nuclear sector
over 40 years ago, the ASSYSTEM Group has achieved an
impressive record of growth and diversification, and the
Group’s client base now covers a broad range of industry
sectors, ranging from Aerospace and Automotive to Nuclear
and Process industries.
<strong>The</strong> ASSYSTEM Energy & Nuclear Business Unit consists of
over .0 Engineers across Europe with a turnover of approx
£145m. Operating within the Civil, Naval & Defence sectors,
Group capabilities include new plant design, construction &
commissioning and the provision of maintenance support and
outage management, to decommissioning and the design and
development of special purpose plant and equipment, including
remote handling systems.
ASSYSTEM has offices located close to most major nuclear
sites in the UK and France, at Preston, Westlakes, Dounreay,
Sunderland, Derby and Bristol in UK; and in France at
Cherbourg, Suresnes, St Quentin en Yvelines, Geneva, Lyon,
Bordeaux, Ardoise, and Marseille. This enables the Group to
provide a network of local support to major clients, backed up
by specialist engineering support from the Group’s Technical
Centres. <strong>The</strong> Groups key clients in the nuclear sector include
AWE, Areva British Energy, EdF, Sellafield Ltd., Rolls-Royce,
UKAEA, CEA, CERN, IRSN.
ASSYSTEM has established an international reputation in
nuclear systems engineering, specialising in the design and
development of a wide range of high integrity plant and
equipment for the nuclear industry.
35

ATKINS STAND: 32
Contact: Nigel Thornton
Woodcote Grove, Ashley Road, Epsom
Surrey, KT18 5BW
UNITED KINGDOM
Tel: +44 (0) 1946 692345
Email: nigel.thornton@atkinsglobal.com
www.atkinsglobal.com
Atkins is involved in the planning, designing and enabling of
complex capital projects. We lead the way in a diverse range of
disciplines, from designing the world’s tallest buildings to
improving the efficiency of major public transport systems.
Atkins is the largest engineering consultancy in the UK, the
fourth largest multidisciplinary consultancy in the world and
the largest multidisciplinary consultancy in Europe. Our size
and expertise bring significant value to our clients, allowing us
to harness an unrivalled pool of creative, professional people to
produce outstanding solutions to challenging problems.
Atkins has been providing support to the nuclear sector for
more than four decades. From civil and structural design for
Berkeley power station in the early 1960’s, we now deliver
multi-discipline solutions across all sectors of the industry.
Today, we are involved in three of the largest engineering
projects within the nuclear sector:
• AWE Design House – Providing multi-discipline teams
for the major capital programme at AWE
• British Energy Technical Support Alliance – Providing
technical support to the operating stations
• Sellafield Legacy Ponds – Part of a Joint Venture with
Aker Solutions and Carillion delivering whole life cycle
projects at the legacy ponds
36
ATTENTIONIT LTD STAND: 40
Contact: Dan Smith
Newton House, Ste 101, Birchwood Park
Warrington, Cheshire, WA3 6FW
UNITED KINGDOM
Tel: +44 (0) 1925 320070
Email: dsmith@attentionit.com
www.attentionit.com
AttentionIT has been assisting facilities since 2001 using our
expertise in environmental waste tracking and consulting
services to stream line processes in the Waste Management
arena. Our software, eMWaste ® tracks and manages all
radioactive, hazardous and mixed waste streams and materials.
eMWaste ® electronically stores all information related to;
characterization, storage, movement, processing, treatment,
shipping, and disposal. eMWaste ® is web-based software,
operating under a secure connection with servers installed at
the CSC facility.
eMWaste ® provides the ability to create and detail
Waste/Material shipments and generate all shipping paperwork
conforming to regulatory requirements of Department for
Transport from a single source. This limits errors and reduces
the amount of time needed for data entry.
AttentionIT also has extensive consulting capabilities. With our
operational experience we can provide knowledge on site
design, waste management, IT configuration and more. We are
looking forward to working with you.
AUGEAN PLC STAND: 36
Contact: Gene Wilson
East Northants RMF, Stamford Road
Kings Cliffe, PE8 6XX
UNITED KINGDOM
Tel: +44 (0)1733 444900
Email: genewilson@augeanplc.com
www.augeanplc.com
Augean PLC is a market-leading UK based specialist waste
and resource management group delivering a broad range of
services to the hazardous waste sector.
We offer a complete solution for the management of hazardous
wastes and work in partnership with our clients to develop long
term answers to the treatment and disposal of their waste and
operates proactively to meet or exceed regulatory standards.
We own more than eight million cubic metres of landfill void
space, seven treatment and recycling centres and employ over
200 people across our eleven sites. We are:
A safety and compliance led business:
• BSI certified for our integrated management system
including environment, health and safety and quality
• Sector leader in the modernisation and introducing new
technologies
• Members of organisations including: Achilles;
Environmental Services Association and Environmental
Industries Commission
At its East Northants Resource Management Facility, Augean
will provide LLW disposal services with the following features:
• LLW of specific activity of up to 200Bq/g
• Radioactive contaminated asbestos
• Radioactive inert, non-hazardous and hazardous wastes
• Wide range of isotopes tailored to the UK inventory
• High radioactive capacity
• Receipt in bags and drums
• Centralised location in the UK

BELGOPROCESS STAND: 28
Belgoprocess brings 50 years of operational experience in
waste management and in decommissioning of nuclear
facilities. We are experts in minimising the amount of
radioactive waste produced and maximising clearance of
decontaminated material while optimising operational costs.
Our integrated nuclear waste management and
decommissioning services include:
• Turnkey solutions for processing and storage of radioactive
wastes and for decommissioning nuclear facilities,
including alpha-contaminated facilities and installations
• Advice on decontamination and dismantling
techniques/methods and on waste processing techniques,
taking into account the stringent safety requirements of
any national or international regulations
• Feasibility tests and demonstration runs in existing
facilities
• Research, development and technical demonstration of
process control techniques
• Characterisation, both chemical, physical and
radiological, of waste streams
• Assistance in the commissioning of nuclear processing
facilities
• Problem solving of existing waste treatment facilities and
optimisation of implemented solutions.
• Capability to process foreign waste of different origins in
our installations
Belgoprocess knows how to decide on strategies for processing
waste and for decommissioning. We also know how to carry
out the careful balancing act between criteria such as worker
dose, environmental impact, financial aspects, technical
constraints, waste storage and disposal capabilities and public
acceptance. This experience, combined with our focus on
40
client-oriented post-commissioning services, make us unique in
the industry.
From providing consulting services in specific areas to
managing entire projects, we are committed to our clients and
to doing the job right, the first time around.
BNS NUCLEAR STAND: 50/51/83/84
SERVICES
PLATINUM SPONSOR
Contact: Liz Pulford
Cambridge Road, Whetstone
Leicester, LE8 6LH
UNITED KINGDOM
Tel: +44 (0)116 201 5346
Email: liz.pulford@babcock.co.uk
www.babcock.co.uk
<strong>The</strong> challenge of decommissioning the UK’s civil nuclear
assets is a challenge that has been embraced by BNS Nuclear
Services. Our decommissioning business has experience in the
retrieval, processing and management of active materials on
sites across the UK and overseas, with projects ranging from
concept design to on site operations and services. Areas of
expertise include:
• Retrieval, analysis and segregation of solid waste.
• Retrieval of sludges and liquids.
• Versatile encapsulation process combining solid and
liquid wastes.
• Ion exchange and effluent management.
• Safety Case support and legislative compliance.
• Waste storage solutions.
• On-site decommissioning services.
In developing the above capabilities, BNS Nuclear Services
have drawn on our strengths in mechanical handling and

emote operations. Our background of systems integration and
equipment supply, coupled with our safety case capability and
our practical hands-on site experience, place us in a unique
position to provide a holistic and comprehensive
decommissioning and waste management service.
CH2M HILL SPONSOR ONLY
SILVER SPONSOR
Contact: www.ch2m.com
CVD NUCLEAR SOLUTIONS STAND: 6
Contact: Mr. Garry Downie
CVD Nuclear Solutions
CVD Building
Coddington Crescent
Motherwell
ML1 4YF
Tel: 0845 450 1701
Email: gdownie@cvdltd.co.uk
www.cvdltd.co.uk
As a progressive company in the field of Nuclear
Decommissioning our mission to provide highly qualified and
competent personnel ensures that the services we offer meet
and exceed the health, safety and environmental needs of the
operating organisations that we serve.
Finding safer and clearer techniques within this sector is vital
and as a consequence are proud to embed innovation at the
heart of our business model; Working closely with our partners,
we have developed specifically designed diamond cutting
segments and pioneered close loop water recycling allowing
for safe drilling into Uranium fuel cells as well as a patented
filtration system which allows for easier capture and disposal
of slurry particles within operations resulting in reduced
generation of waste. By combining best practice techniques
with our innovation capability, the potential for the creation of
new hazards from decommissioning activity will be
significantly reduced.
Our Services:
• Diamond Drilling and Cutting
• Dry Diamond Wire Sawing (>99.98% Dust Capture)
• Diamond Wire Technology for in-cell size reduction and
demolition
• Remote Controlled Robotic Demolition
• Training capability to enable mitigation and effective
management of the Socio-Economic impact of
decommissioning activity
DAHER STAND: 55
Contact: Mr. Jason Podmore
DAHER
Amberley Drive
Sinfin Lane
Sinfin
DERB
DE24 9RE
Tel: +44(0)1332 274 373
Email: j.podmore@daher.co.uk
www.daher.co.uk
<strong>The</strong> DAHER Group is an European integrated equipment and
services supplier, dedicated to Nuclear, Defence, Aerospace
and Automotive sectors with three principal activities;
transport, service, and manufacturing, that combined, enables
DAHER to create an integrated offering.
DAHER’s UK turnover during 2008 was c£12.7m generated
from 145 employees. Worldwide, 2008 turnover was c€609m
generated from 7,000 employees.
In the nuclear industry, DAHER undertakes design,
development, manufacturing and licensee activities to produce
handling and packaging equipment for transport and
warehousing of radioactive fuel and waste.
DAHER also offers a complete transport service within the
nuclear fuel cycle and for nuclear research centers, including
UF6, UO2, irradiated fuel assemblies and radioactive waste.
Our DAHER facility in Germany (NCS) not only has design
and manufacture capability but also a repository as part of its
portfolio.
DAHER currently supports, amongst others, Sellafield Ltd.,
UKAEA and the Rutherford Appleton Laboratory in the UK
and CEA, EDF and AREVA in France as well as GNS,
NUKEM and URENCO in Germany.
DEWDROPS STAND: 45
BRONZE SPONSOR
Contact: Dr. Albert JACOBS
219 Avenue du Marechal Leclerc
59450 Sin Le Noble
FRANCE
Tel: +33 327 904 334
Email: dewdrops@dewdrops.fr
www.dewdrops.fr
Dewdrops is an independent French company based in Sin le
Noble in the north of France, 20 minutes away from Lille and
less than an hour from Paris Charles de Gaulle airport by direct
express train. Dewdrops provides a full treatment service for
toxic waste oils and solvents with a special capacity in the
nuclear field. Our state-of-the-art patented technology enables
41

us to eliminate a wide range of mixtures of radioactive oils.
Together with a volume reduction factor of at least 20 times,
the process combines reliability and versatility with a minimal
environmental footprint. <strong>The</strong> proprietary mobile plant cuts out
customer investment and heritage costs and brings risks under
control. <strong>The</strong> nominal unit treatment capacity is 100 liters per
day with the actual production depending on the exact nature of
the liquid to be treated. Year in year out, Dewdrops devotes
more than 20% of its resources to develop constantly improved
solutions for our customers. In October 2009, as a bronze
sponsor, we will be welcoming our international customers at
our stand at the ICEM09 exhibition hall.
DIAMOND DETECTORS LTD STAND: 5
Contact: Alex Brown
16 Fleetsbridge Business Centre
Upton Road, Poole, Dorset, BH17 7AF
UNITED KINGDOM
Tel: +44 (0)1202 441031
Email: alex.brown@diamonddetectors.com
www.diamonddetectors.com
“From Concept through Design & Prototype to Manufacture”
DDL design and manufacture resilient CVD Diamond based
devices for monitoring and measuring radiation.
In 2008 BAE Systems purchased a 50% share in Diamond
Detectors Ltd (DDL) a subsidiary set up by Element Six, the
world leader in the development of Chemical Vapour
Deposition (CVD) diamond technology.
DDL’s mission is to develop a range of “resilient radiation
detectors” and packaged devices for civil nuclear applications
through research and partnership with academia and industry.
DDL’s expertise includes world class diamond processing with
surface roughness

GOLDSIM STAND: 58
TECHNOLOGY GROUP
Contact: Ian Miller
300 NE Gilman Blvd., Suite 100
Issaquah WA 98027
USA
Tel: +1 425-295-6985
Email: IMiller@GoldSim.com
www.GoldSim.com
Originally funded by the United States Department of Energy,
JAEA and ENRESA, GoldSim is a software tool that is used
worldwide for long-term safety assessment of radioactive
waste repositories and contaminated sites. GoldSim has been
used to model existing and proposed radioactive waste disposal
facilities in the US, the UK, Japan, South Korea, Taiwan,
China, France, Germany, and Spain, amongst others. GoldSim
is also widely used for other environmental applications,
ranging from municipal water resource management to mine
water quality management.
GRAVATOM STAND: 1
Gravatom Engineering Systems Limited designs, manufactures
and commissions engineering solutions worldwide. Bought by
ONET Technologies at the end of December 2008, the
acquisition enhances the range of products and services
supplied by Gravatom to the nuclear industry and adds a vast
range of remediation, decommissioning, decontamination and
new build capability and expertise build up by ONET in France
over the past 30 years.
Our UK clients include AMEC plc, AWE plc, Babcock Marine,
British Energy plc, GE Healthcare Ltd, NDA, NNL, UKAEA
plc, Varian Medical Systems Inc, VT Projects ONET are the
principal decommissioning contractor in France working for
CEA, Edf and AREVA. ONET Technology also has the unique
ability to provide front end risk assessments and safety case
studies before or in parallel with optioneering and design
schemes.
We provide support and facilitation at every stage of the
project. Our capabilities extend to:
• Feasibility Studies
• Cost Options
• Project Initiation
• Mock Up and Prototype Development
• Design and Specification
• Manufacture, Supply and Installation
• Commissioning, Qualification and Validation
• Support Services including compliance, monitoring,
training, servicing and spares.
GREIF UK LTD STAND: 11/12
Contact: Lynne Brown
Greif UK Ltd, Merseyside Works, Oil Sites Road,
Ellesmere Port, Cheshire CH65 4EZ
UNITED KINGDOM
Tel: + 44 (0) 7720 040115 / + 44 (0) 151 373 2000
Email: lynne.brown@greif.com
www.greif.com
Greif was founded in 1877 and is a world leader in industrial
packaging products and services. <strong>The</strong> company creates
competitive advantage for its customers through extensive
experience in steel, plastic, fibre and protective packaging for
various industries and applications. In the United Kingdom
Greif have two manufacturing facilities, specialising in the
production of mild steel, galvanised steel and stainless steel
containers with capacities ranging from 5 litres to 500 litres,
43

many of which are UN approved. Having such a diverse choice
of products and services to offer, we are able to supply
containers to many different markets which include the
chemical, nuclear and pharmaceutical industries. We offer an
extensive range of standard products along with the skills and
technology to allow us to design and develop containers to
meet our customers individual requirements.
HALLIN ROBOTICS LIMITED STAND: 42
Contact: David Arnold
Unit 10, Cross Lane Estate
Seascale, Cumbria, CA20 1EZ
UNITED KINGDOM
Tel: +44 (0)1946 729770
or
Unit E, Riccal DriveYork Road Business Park
Malton, North Yorks. YO17 6YE
UNITED KINGDOM
Tel: +44 (0)1653 697514
Email: enquiries@hallinrobotics.com
www.hallinmarine.co.uk
Hallin Robotics specialises in providing innovative and
practical remote engineering solutions for the nuclear and
offshore markets. We have built up a first-class team of
engineers who have developed a deep understanding of the
technicalities of remote engineering and decommissioning to
produce industry-leading solutions all supported by a mature
supply chain.
Hallin implements HSE Management based on OHSAS18001
and operates an ISO9001 Quality Management System. All
Remote solutions are operated by Hallin Robotics employees.
Full training can also be given to client operators to supplement
remote operations. We have rig hall space available for fullscale
test rigs, to verify functionality and assist stakeholder
management.
Hallin Robotics offers a turnkey delivery service including:
• Project Management
• Optioneering
• Risk Management
• Nuclear safety case
• Scheme design
• Detailed design
• Documentation support
• Management of manufacture and assembly
• Environment characterisation: laser scanning; ground
radar
• Installation and commissioning of remote solutions
• Operation of remote handling equipment
Commercially our team is aware of the shifting context of
delivery, the need to demonstrate value for money and the
overall balance of managing the legacies whilst reducing the
hazards to protect people and the environment.
INTERNATIONAL STAND: 69/70
NUCLEAR SERVICES
Contact: Nick Bold
Pelham House, Calderbridge,
Cumbria CA20 1DB
UNITED KINGDOM
Tel: +44 (0)1925 802656
Email: nick.m.bold@innuserv.com
www.innuserv.com
<strong>International</strong> Nuclear Services Limited (INS) is a wholly
owned subsidiary of the Nuclear Decommissioning Authority
(NDA) in the UK.INS has a dual role; as a commercial and
44
contract management agency for the NDA and as the world’s
most experienced shipper of nuclear materials internationally.
As the NDA’s commercial and contract management agent,
INS manages contracts and relationships, on behalf of the
NDA, with utility customers in the UK and overseas for
services from the Sellafield site, such as the storage and
recycling of irradiated nuclear fuel.
INS has safely transported radioactive cargoes worldwide for
over 40 years. Our subsidiary company, Pacific Nuclear
Transport Ltd is the world’s most experienced shipper of
nuclear materials with a fleet of INF3 class ships. We provide a
complete transport service to our customers, from the design of
nuclear transport packages through to transportation of nuclear
materials using our dedicated fleet of ships.
INS provides complete solutions to customers for their
irradiated nuclear fuel management and transportation needs.
We have the capability to offer our customers a range of
consultancy services, strategic assessments and feasibility
studies on irradiated fuel management. We also advise utility
customers and government agencies on their strategic and
technical options relating to the nuclear fuel cycle.
INUTEC (FORMERLY WMT) STAND: 71
Contact: Kevin Butter
B44, Winfrith, Dorchester
Dorset, DT2 8WQ
UNITED KINGDOM
Tel: +44 (0)1305 202291
Kevin.butter@wmt.co.uk
www.Inutec.co.uk
Inutec is a specialist provider of an integrated offering on
radioactive waste management services, covering the full
Waste Cycle through application of our technical expertise and
operation of unique facilities on our Licensed Site to the UK
and overseas nuclear market. Inutec has the ability for both onsite
and off-site Waste Processing and holds a unique UK
Tritium Waste Capability.
Few companies in the UK can offer similar depth and breadth
of resource and expertise or the comprehensive range of
Radioactive Waste Management capabilities. INUTEC is able
to provide a full range of services for Radioactive Waste
Management and Decommissioning, including:
• Waste Management Assessments and Consultancy
• Waste Sampling and Characterisation
• Advanced Waste Treatment Processes
• Recycling, Recovery and Recategorisation (e.g.
Detritiation)
• Waste Packaging and Immobilisation
• Impact and Fire Testing of Transport Packages
• Radioactive Materials Transport
• Analytical and Radiochemistry
• Waste Management Plant Optimisation, Design Review
and Validation
Inutec has wide experience of the UK regulatory requirements
for both plant and processes, including the NDA LoC process,
specifications and disposal concepts, the safety requirements
for a nuclear licensed site and environmental regulation and
legislation.

JFIMS & JFN STAND: 67
Contact: JFIMS JFN
Alan Lewis Steve Tulk
Factory Road Ennerdale Mill
Sandycroft Egremont
Deeside Cumbria
Flintshire, CH5 2QJ CA22 2PN
UNITED KINGDOM UNITED KINGDOM
Tel:+44 (0)1244 520058 Tel: +44 (0)1946 823502
Contact@JFIMS.co.uk Contact@JFNL.co.uk
www.jfims.co.uk www.jfnuclear.co.uk
James Fisher Inspection and Measurement Services Limited
(JFIMS) provides inspection and measurement capabilities for
the nuclear, defence, homeland security, aerospace, offshore
and other industries. <strong>The</strong> core business of JFIMS is the
measurement and application of radiation. In partnership with
international market leaders the company offers a range of
products and services addressing radiation measurement,
radiological protection, non destructive testing (NDT) and
industrial radiography.
JFIMS aims to deliver products and services to a high standard
and lays great emphasis on the importance of safety, quality
and the impact of the Company’s operations on the
environment.
JFN provides remote handling, engineering, design, trialling,
training, development and plant characterisation services, to
nuclear and industrial clients operating in challenging
environments. JFN focuses on delivering robust, reliable,
maintainable and above all cost-effective solutions for working
in hostile and harsh environments whilst taking care to operate
in a safe and environmentally friendly manner and meet
customers quality requirements
With over 20 years experience working with robotic arms,
manipulators and ROVs, JFN have the experience to tackle
almost any remote handling challenge including the
deployment of our plant characterisation tools into tough and
unfriendly surroundings.
JORDAN NUCLEAR STAND: 68
Contact: Rod Fretwell, Business Development Manager
Kelton House
Westlakes
Cumbria, CA24 3HX
UNITED KINGDOM
Tel: +44 01946 591915
Email: info@jordannuclear.co.uk
www.jordannuclear.co.uk
‘Excellence in the safe reliable delivery of nuclear engineering’
Jordan Nuclear is a well established business offering its
clients ‘total capability’ multi-discipline, nuclear and process
engineering services. We are equipped to handle asset
management and support, new build, refurbishment and
decommissioning services utilising our highly skilled and
experienced teams.
For over 40 years we have developed working relationships
with all of the UK’s atomic and nuclear agencies plus many
leading construction, engineering and manufacturing
companies.
LLW REPOSITORY LTD STAND: 74/75
Contact: Martin Walkingshaw
Greengarth Business Centre, Glengdale Court
Holmrook, Cumbria, CA19 1UL
UNITED KINGDOM
Tel: +44 (0) 19467 22263
Email: martin.walkingshaw@llwrsite.com
www.llwrsite.com
LLW Repository Ltd is the site licence company responsible
for the operation and future development of the UK National
Low Level Waste Repository, located near the village of Drigg
in West Cumbria.
LLW Repository Ltd provides a range of services for waste
producers in many sectors, ranging from defence to healthcare.
Our primary services include:
• Disposal of compactable and non-compactable solid Low
Level radioactive waste, (LLW).
• Treatment of LLW prior to final disposal (including
supercompaction, thermal treatment and metallic waste
recycling).
• Provision of approved LLW transport and disposal
containers for national and international use.
• Advice and guidance on all aspects of waste
characterisation, forecasting, packaging and transport
• Decision Support – participation at all levels in waste
management options studies and assessments
In addition, LLW Repository Ltd is proud to be working in
partnership with the UK Nuclear Decommissioning Authority
(NDA) to develop and implement an integrated strategy for the
management of Low Level Radioactive Waste across the UK.
LOKRING TECHNOLOGY LLC STAND: 10
Contact: Martin Parker
Lokring Europe Ltd
Monument Crescent
Shawfarm Industrial Estate
Prestwick
Scotland
KA9 2RQ
Tel: (44) 1292 678866
Email: mparker@lokring.com
www.lokring.com
<strong>The</strong> shortage of skilled labour, in particular pipe welding
ability, and the need to minimise exposure of personnel to
radioactive environments, are two practical constraints faced
by the Nuclear Industry. Lokring Technology LLC provides a
cost effective solution to these issues.
Lokring eliminates hot work issues by utilising patented Elastic
Strain Preload technology. Lokring produces permanent,
leak free, weld equivalent pipe connections, in a fraction of the
time required for welding, without the need for highly skilled
personnel. A three point visual inspection confirms correct
installation, eliminating the need for X-rays or other expensive
NDT methods.
Additional Benefits of Lokring include the elimination of
airborne contamination due to welding, no need to dry systems
prior to installation, lower overall cost and faster project
completion times.
Lokring Stainless and Carbon Steel Connectors are qualified to
ASME B31.1/B31.3 Pressure Piping Codes, with a history of
over 30 years use in the process industries, Lokring is used
extensively on Nuclear Power Stations and Processing facilities
in the UK, North America, Scandinavia and other countries.
Approved by the UK Ministry of Defence, Lokring are
45

currently used in the construction of the UK Nuclear
Submarines Programme.
Please attend our stand for a demonstration.
MECH-TOOL
ENGINEERING LTD STAND: 38
Contact: Phil Dunn
Mech-Tool House, Whessoe Road
Darlington, Co Durham, DL3 0QT
UNITED KINGDOM
Tel: +44 (0)1325 355141
Email: sales@mechtool.co.uk
www.mechtool.co.uk
Mech-Tool Engineering is a successful global supplier of
Packaged Equipment Modules, Industrial Noise Control
Products and Passive Fire & Explosion Protection Solutions.
We provide a complete design, project management and supply
service for:
• Packaged Equipment Modules
• Acoustic Noise Control and Mitigation
• Fire and Blast Protection
Capabilities
• In-house design and engineering capability
• State of the art 3D engineering
• Lloyds/DNV certified fire resistance to J60/H120 and
blast up to 4 bar
Products & Services
<strong>The</strong> company offers an extensive range of specialist products
and services including:
• Modules & Enclosures
46
• Purpose designed for specified explosion, fire, seismic
and acoustic performance
• Venting Systems
Rapid opening times on reaching trigger point
Pressure and temperature sensitive options available
• METLAG System
All metallic thermal insulation for RPV’s, SG’s,
pressurisers, pumps, primary and auxiliary pipework
• Re-Fuelling Pond Liners
Factory built modular sections, assembled on site to
provide integral shuttering for structural concrete pour
• Industrial Noise Control
Rotating machinery and power plant including turbines,
generators, compressors etc
NAC INTERNATIONAL STAND: 25
Contact: Juan C. Subiry
3930 East Jones Bridge Rd.
Norcross GA 30092
USA
Tel: +1 678 328-1282
Email: jsubiry@nacintl.com
www.nacintl.com
NAC <strong>International</strong> (NAC) is an industry-leading provider of
engineering and nuclear fuel management solutions for nuclear
facility operators, fuel cycle companies and government
agencies. <strong>The</strong> company offers a proven process for the design,
licensing and deployment of innovative technologies to store,
transport and manage nuclear materials, including waste and
spent fuel. In 2009, NAC received the U.S. NRC Certificate of
Compliance for the MAGNASTOR System dry storage
technology, offering spent fuel storage capacity and operational
advantages superior to those of any other concrete, canister-

ased system. Our professional staff possesses unsurpassed
industry knowledge and experience, necessary for today’s
demanding requirements for nuclear project management and
performance. NAC is also a leading provider of nuclear spent
fuel transportation services and operates a commercial fleet of
spent fuel transport casks.
In addition, NAC’s Consulting division continuously serves the
world’s most prestigious nuclear organizations in providing
impartial evaluation, consulting and training services in all
technical and business aspects of the nuclear fuel cycle. No
matter how complex the nuclear market may become, NAC’s
specialized consultants will be there to provide well-informed
analysis. NAC’s unique reputation for customer-centric service
is reinforced by its diverse customer portfolio of the world’s
leading nuclear organizations.
NATIONAL NUCLEAR STAND: 46/47
LABORATORY (NNL)
<strong>The</strong> UK’s National Nuclear Laboratory provides an extensive
and integrated range of technology services and solutions based
on a powerful combination of knowledge, experience and
unique facilities.
Our technology services underpin the full life cycle of nuclear
facility decommissioning. <strong>The</strong>y are based on over 40 years
experience and knowledge of legacy wastes found on nuclear
sites. Key services include: strategy development; waste
sampling and characterisation; waste retrieval; wasteforms and
waste processes.
<strong>The</strong>se services are supported by a broader offering of products
and services across the nuclear fuel cycle:
• Homeland Security and Non-Proliferation
• Nuclear Science
• Waste and Residue Management
• Plant Process Support
• Materials, Corrosion and Nuclear Chemistry
• Environmental Management
• Specialist Analytical Services
NIS LTD STAND: 53
Contact: Phil Monks
Ackhurst Road, Chorley
Lancashire, PR7 1NH
UNITED KINGDOM
Tel: +44 (0)1257 265656
Email: sales@nisltd.com
www.nisltd.com
Providing professional engineered solutions to complex
challenges demands a broad and diverse range of capabilities.
At NIS we are proud to offer a comprehensive range of
services that provide customers with the flexibility they need to
bring value to their projects, whatever the size, and at whatever
stage of maturity.
From front end definition and engineering consulting services,
through detailed design, in-house manufacture, installation and
commissioning, NIS bring a wealth of knowledge and
experience to assist in turning your concept into reality.
With an ingrained culture of Safety and Innovation, NIS
delivers across a wide range of markets, including the Nuclear,
Industrial, Security, Aerospace and Food sectors. This broad
industry presence provides excellent opportunities for
technology transfer, particularly in our specialist field of
equipment integration and automation.
Our custom built facilities in the North West of England are
complemented by a number of strategically placed customer
facing premises and further enhanced by additional
manufacturing capability in NIS China.
47

48
Dedicated procurement specialists ensure access to a global
supply chain, optimising value for money whilst maintaining
the highest levels of quality assurance through an ongoing
process of supply chain evaluation and management.
NSG ENVIRONMENTAL LTD STAND: 52
SILVER SPONSOR
Contact: James Rudd
Scientia House, Western Avenue
Matrix Park, Chorley, PR7 7NB
UNITED KINGDOM
Tel: +44 (0) 1772 458818
Email: sales@nsgltd.com
www.nsgltd.com
NSG Environmental Ltd has been providing Decommissioning
and Waste Management Services to the UK civil and defence
nuclear installations for more than 25 years. Our team is made
up of experienced scientists, engineers and decommissioning
operatives with many years’ experience of working in the
nuclear industry.
NSG has successfully completed projects on many of the UK’s
nuclear facilities, working with asset owners including
Sellafield, AWE, Magnox, and UKAEA, in radiological
conditions ranging from C2 to C4 and R2 to R4.
Our Site Operations Teams provide the following services:
• Installation
• Refurbishment and asset support
• Decommissioning
• Plant operations
• Radiological protection services
• Land remediation
Our Technical Services department specialise in the provision
of development programmes that support the nuclear
decommissioning and waste management industry. We have

assembled a team whose guiding principle is to find practical
and “fit for purpose” solutions that acknowledge existing
technologies, whilst pushing the boundaries of innovation.
We provide the following services:
• Test rig design and operation
• Technical consultancy
• Waste retrieval and processing
• Laboratory services
• Waste simulation
NUCLEAR FILTER STAND: 59
TECHNOLOGY
Contact: Terry Wickland, President
741 Corporate Circle
Suite R, Golden, Colorado 80401
USA
Tel: +1 303 384 9785
Email: terry@nucfil.com
www.nucfil.com
Nuclear Filter Technology (NucFil) is a small, minority-owned
business dedicated to providing packaging, shielding and
characterization technologies for transport, ventilation, storage
and disposal of radioactive and mixed waste. NucFil has
provided nuclear grade products and services to Department of
Energy weapons-complex sites since 1986, utilizing a
specialized staff of scientists and engineers who design,
fabricate, and test all products to meet quality requirements of
ANSI/AMSE Nuclear Quality Assurance-1 (NQA-1). NucFil
has well established Environment, Safety and Health (ES&H)
and Quality programs in place.
NucFil’s capabilities and experience include design,
fabrication, testing and certification of nuclear grade products
such as:
• Nuclear Material Storage Containers
• Radioactive Waste Bags
• Mobile Gas Analytical Equipment
• Drum Vent Filters
• Mobile Drum Venting Systems
• Remote Handled Transuranic (RH-TRU) Drum Venting
Equipment
• Non-sparking dart filters/sample ports
• Finite Element Analysis
• Sampling Tubes for Uranium Hexafluoride
NUCLEAR INDUSTRY STAND: 79
ASSOCIATION (NIA)
Contact: Amanda MacMillan
Carlton House, 22a St James’s Square
London SW1Y 4JH
UNITED KINGDOM
Email: Amanda.macmillan@niauk.org
www.niauk.org
<strong>The</strong> Nuclear Industry Association (NIA) is the trade association
and representative voice of Britain’s civil nuclear industry. It
represents more than 170 companies and some 40,000 UK
nuclear workers, including the operators of the nuclear power
stations, those engaged in decommissioning, waste
management, nuclear liabilities management and all aspects of
the nuclear fuel cycle. It also represents nuclear equipment
suppliers, engineering and construction firms, nuclear research
organisations, and legal, financial and consultancy companies.
<strong>The</strong> NIA supports a diverse energy mix for the UK including
clean coal, gas, renewables and nuclear.
NUCLEAR TECHNOLOGIES STAND: 23
Contact: Mrs. Agnes Ross
Sinclair Building
Janetstown, Thurso, KW14 7XF
UNITED KINGDOM
Tel: +44 01847 805070
Email: agnes.ross@nuclear.co.uk
www.nuclear.co.uk
Nuclear Technologies is a leading supplier of professional
scientific and engineering consultancy to the UK nuclear
industry specialising in:
• Environment and Radioactive Waste
• Safety and Radiation Physics
• Decommissioning Projects and Engineering
<strong>The</strong> company, founded in 1994, is firmly established as a
premier nuclear supplier with over 100 Consultants and a
turnover of £6.3m in 2008.
Nuclear Technologies was acquired by TÜV SÜD (UK) Ltd in
August 2006 providing us with international expertise from this
major German regulator. TÜV SÜD Industry Services division
supplies engineering, testing and inspection services for
manufacturers/operators of process-engineering plants,
buildings and infrastructural facilities.
Many of our Consultants are internationally recognised experts
with outstanding records of achievement in the nuclear industry
through previous employment in major nuclear companies,
providing the company with valuable hands-on experience of
facilities and operations on the main British nuclear sites.
Nuclear Technologies has a forward looking approach to
business allowing us to encompass the evolving needs of the
UK nuclear industry. This is further underpinned by an
enthusiastic staff development programme ensuring we have a
range of staff at varying levels and can deploy high calibre
senior staff, supported by well motivated junior consultants to
ensure an overall competitive service.
NUKEM STAND: 24/27
TECHNOLOGIES GMBH
Contact: Beate Scheffler
Industriestr. 13, 63755
Alzenau
GERMANY
Tel: +49 6023 911147
Email: beate.scheffler@nukem.de
www.nukemgroup.com
NUKEM Technologies GmbH is a leading service provider for
the nuclear industry world-wide. Main business activities
include the management of radioactive waste,
decommissioning, and engineering.
<strong>The</strong> company’s waste management program comprises a broad
spectrum of services ranging from the development, delivery
and operation of radioactive waste treatment systems (e.g.
sorting stations, evaporation, cementing and incineration
systems, high-pressure compactors, etc.) to the construction of
complete waste treatment centers.
NUKEM’s long-standing experience and successful projects
like the decommissioning and dismantling of the Kahl Nuclear
Power Test Plant in Germany underline the company’s role as
perfect partner for all decommissioning tasks.
<strong>The</strong> Group`s Engineering and Consulting services play an
important role in contributing to innovative design and build.
In particular, NUKEM possesses the technology leadership in
HTR fuel technology.
49

Consistent customer orientation and quality management are
essential cornerstones of NUKEM’s corporate philosophy. <strong>The</strong>
company places a high premium on individualized service,
timely project completion, complete and understandable
documentation and providing its customers with superiorquality
products.
NUVIA LIMITED STAND: 43/44
SILVER SPONSOR
Contact: Judith Horsley
Kelburn Court, Daten Park, Risley,
Warrington, WA3 6TW
UNITED KINGDOM
Tel: +44 (0) 1925 858 200
Email: info@nuvia.co.uk
www.nuvia.co.uk
Nuvia brings together the nuclear experience and expertise of
Nuvia Limited in the UK and the five companies that form
Nuvia France: NTS, Salvarem, Mecatiss, Millennium, and
Essor. Together the 1500 staff generate a turnover of more than
200 M€ per annum.
Nuvia is one of five businesses that form Soletanche
Freyssinet. With over 20,000 staff and a turnover in excess of
2,5 B€, Soletanche Freyssinet is a world leader in specialised
civil and geotechnical engineering and has a long history of
involvement in the nuclear industry through worldwide use of
its advanced engineering and specialist products.
Soletanche Freyssinet is a wholly owned subsidiary of VINCI,
the world’s largest integrated concessions and construction
group.
<strong>The</strong> Nuvia Group has five core activities: new build, plant life
extension, radiation safety services, decommissioning and
waste management. At a more detailed level the Company’s
capabilities range from front-end consultancy through design
and build to operation and final liabilities management.
Nuvia Limited’s breadth and depth of experience is enhanced
by an understanding of international best practice developed
through global operations and has resulted in the Company’s
proven ability to deliver practical and cost-effective solutions
to the most demanding problems faced by the nuclear industry
today.
ORTEC STAND: 31
Contact: Trevor Hatt
Advanced Measurement Technology
Spectrum House, 1 Millars Business Centre
Fishponds Close, Wokingham. RG41 2TZ
UNITED KINGDOM
Tel: +44 (0)118 936 1210
Email: ortec.uksales@ametek.co.uk
www.ortec-online.com
ORTEC is a global supplier and world leader in the
development and manufacture of nuclear and radiological
detection instrumentation, specialising in high-resolution
gamma-ray spectrometer systems, based on High Purity
Germanium (HPGe) detectors, as well as a wide range of other
detection technologies for gamma and neutron, and charged
particle detection. HPGe detectors are widely recognised as the
best detection technology for positively identifying
radionuclides.
<strong>The</strong> ORTEC product line of over 1600 products includes
instruments and systems for nuclear power plant and
government nuclear facility operations, waste assay, special
nuclear materials safeguards, search and identify operations,
and chemical weapons identification.
50
ORTEC continues to lead the industry in innovative techniques
and equipment to perform the most rigorous of measurements.
Specifically for site characterisation measurements and the
quantification of specific activities in and on surfaces such as
walls, floors and in soils, the ORTEC ISO-CART and ISOPlus
software, provides a complete solution for a variety of needs.
In conjunction with a portable, HPGe spectrometer (TRANS-
SPEC) it is possible to undertake extensive measurements in
the field. Also available is the lightweight, rugged digiDART
specifically designed for use in-situ. <strong>The</strong> digiDART can be
used with HPGe, Lanthanum Bromide or NaI detector
technology.
OXFORD TECHNOLOGIES LTD STAND: 20
Contact: Stephen Sanders
7 Nuffield Way
Abingdon, Oxon, OX14 1RJ
UNITED KINGDOM
Tel: +44(0)1235 522119
Email: stephen.sanders@oxfordtechnologies.co.uk
www.oxfordtechnologies.co.uk
Staff at Oxford Technologies Ltd have been delivering creative
solutions to challenging engineering problems in hostile
environments for over 15 years.
<strong>The</strong> company was formed by the team of engineers and
operators who developed and operated the remote handling
facilities for the maintenance of JET, the world largest nuclear
fusion machine. This team grew and went onto develop remote
maintenance concepts for some of the worlds most challenging
nuclear projects including the multi-billion euro ITER fusion
machine, the nuclear transmutation device MYRRA (SCK-
CEN), Dounreay Shaft & Silo decommissioning (D3200) and
many more.
Today we provide a wide range of professional engineering
services for clients engaged in manipulation of plant in hostile
environments. Our deep experience in manipulator and tooling
technologies and remote operations implementation provides
the platform to deliver cost effective and fit-for-purpose
solutions to our clients.
Our track record for client satisfaction is second to none and is
evidenced by our exceptional record of winning projects from
returning customers.
Our unique experience has recently taken us into space, where
we are working with some of the biggest players in this field to
design remote systems for the European EXOMARS project.
Oxford Technologies provides innovative solutions based on
sound experience.
More information about Oxford Technologies services can be
found on our website at www.oxfordtechnologies.co.uk
PACTEC, INC. STAND: 72
BRONZE SPONSOR
Contact: Stuart Bowe Wendall Reeves
PacTec, Inc. UK Mike Sanchez
<strong>The</strong> Gate House PacTec, Inc. USA
Calder Abby P.O. Box 8069
Calderbridge, Cumbria Clinton, LA 70722
CA20 1DZ Tel: +1800-272-2832
Tel: +44 07775 895 818 wendallreeves@pactecinc.com
stuartbowe@pactecinc.com mikesanchez@pactecinc.com
www.pactecinc.com
PacTec, Inc. has over 20 years experience in the quality
manufacturing of soft sided containers/packaging for the
radioactive waste, and hazardous waste industries. PacTec
specializes in providing custom designed products for our

demanding clients, and we also offer a wide range of project
proven standard items for your immediate needs. Our client list
includes URS/Washington Division, Energy Solutions, CH2M
Hill, and Bechtel Jacobs. Our products have been used on
several DOE sites across the US; Idaho National Labs, Oak
Ridge, Hanford, Rocky Flats, Fernald, and Los Alamos. We
also work with commercial nuclear sites providing containers
and packaging for Entergy Nuclear, Cameco Corporation,
Duke Energy, and Exelon.
Our product line includes IP-1 and IP-2 lift bag containers,
LSA and SCO wraps, rail car liners and tarps, disposable
polyethylene container liners, tarpaulins and accessories, spill
containment berms, dewatering filters and liners, specialized
waste bags, known as bladder or vacuum bags, and
soil/remediation covers. We stock a large inventory of products
for immediate shipping, and we also provide quick turn around
for our custom engineered and designed products. Contact our
UK sales director Stuart Bowe at 07775 895 818 or call
Wendall Reeves or Mike Sanchez at our US office at 800-272-
2832. www.pactecinc.com
PAR SYSTEMS, INC. STAND: 19
Contact: Karen Knoblock
707 County Road E. West
Shoreview, MN 55126-7007
USA
Tel: +1 651 528 5275
Fax: +1 651 483 2689
Email: kknoblock@par.com
www.par.com
PaR Systems is a leader in the design, manufacture and
installation of large scale systems for nuclear and
decommissioning markets throughout the world. PaR provides
systems for size reduction and hazardous material handling.
Products for hazardous environments include telerobotic
manipulators, powered manipulators, robotic systems and
transporters, including in-cell cranes.
Since 1961 PaR Systems has been providing specialized
material handling and automation equipment to many diverse
industries, including aerospace, defense, Department of
Energy, food and beverage, government, hazardous material
management, industrial manufacturing, life sciences, marine,
semi-conductor, and other specialized markets.
PaR has focused on the application of large scale, as well as
small and precise, high-accuracy, robotic and material handling
equipment and systems solutions for critical customer
applications. PaR Systems’ experience began with the
development of manipulator systems when the growth of the
nuclear industry created a demand for remote handling
equipment. Since then PaR has evolved this technology for
robotics across a variety of market segments, increasing its
expertise to provide equipment for a variety of specialized
applications, building on the automation capability developed
across a wide range of demanding commercial, government
and defense segments.
PROJECT TIME & COST UK STAND: 62
LTD/PROJECT TIME & COST INC
Contact: PT&C UK Ltd PT&C Inc
J. Michael Devine Andrew Reape
Westlakes Science & 2727 Paces Ferry Road,
Technology Park Atlanta, GA 30339
Innovation Centre, USA
Moor Row Tel: +1 770.444.9799
Cumbria CA24 3TP Email:
UNITED KINGDOM andy.reape@ptcinc.com
Tel: +44 (0) 1946 693144 www.ptcinc.com
Email: mike.devine@ptcinc.com
www.ptcinc.com
Project Time & Cost is the leading provider of professional,
independent, total cost engineering, project and program
management, and risk analysis services to both the public and
private industry sectors. Our effective application of best
practice cost engineering methodologies has been proven to be
the key to achieving project success. We can help deliver your
project on time and within budge.
With more than 27 years of experience, PT&C and PT&C UK
are committed to providing every client <strong>The</strong> Right
Answer...Right Now ® .
REMEDI8 STAND: 54
Contact: David Lewis
Scientia House, Western Avenue
Matrix Park, Chorley, PR7 7NB
UNITED KINGDOM
Tel: +44 (0) 7970700894
Email: sales@nsgltd.com
www.nsgltd.com
<strong>The</strong> Remedi8 alliance consists of a team made up of seven
Companies who together are experienced in delivering multi
disciplined decommissioning projects. Remedi8 recognises the
importance of Customer involvement throughout the project
lifecycle and one of our underlying principles is Client
involvement from start to finish on each project. With this in
mind, we work to form an integrated team with the Customer
who in turn, becomes the eighth member of the Project Team -
completing the Remedi8 alliance.
<strong>The</strong> Remedi8 alliance has a wealth of knowledge in the
decommissioning of contaminated facilities on the majority of
51

UK Nuclear Licensed Sites. Having experience as a Team on
previous projects working in radiological contaminated areas
ranging from C2/C4 and R2/R4, Remedi8 is well placed to
respond and adapt to both client and site requirements.
<strong>The</strong> key feature of our team is that we are solely focused on
decommissioning projects which brings benefit to our clients
by the transfer of knowledge and techniques from previous
projects.
Remedi8 have a clear understanding of the complex
requirements for decommissioning which enables us to develop
fit for purpose, cost effective and timely decommissioning life
cycle solutions.
S.A. ROBOTICS LTD STAND: 22
Contact: Christopher Woodhead
Whitehaven Commercial Park, Moresby Parks
Whitehaven, Cumbria, CA28 8YD
UNITED KINGDOM
Tel: +44 (0)1946 66680
Email: ukinfo@sarobotics.com
www.sarobotics.com
S.A. Robotics is an advanced technology and engineering
company. We design, build, test, and deploy an array of remote
handling, robotic, and containment systems and equipment in
use throughout the nuclear industry.
S.A. Robotics’ innovative systems and equipment are deployed
in some of the world’s most hazardous environments. We
specialise in a concept-to-creation fast-track delivery of remote
and robotic arms and manipulators, specialty tooling,
hazardous and radioactive containment structures, gloveboxes,
and waste handling and packaging systems.
SELLAFIELD LTD STAND: 65/66
Contact: Joanne Gavin
Email: joanne.gavin@sellafieldsites.com
www.sellafieldsites.com
Sellafield Ltd has two sites – Sellafield in West Cumbria and
Capenhurst in Cheshire.
Across our business we are carrying out some of the most
innovative and complex nuclear activities in the world.
Our site at Sellafield is spread across 6 square miles and is
home to more than 1,000 facilities, all performing a wide range
of tasks. <strong>The</strong>se include decommissioning the UK’s nuclear
legacy as well fuel recycling, manufacturing and the
management of low, high and intermediate level nuclear waste.
At Capenhurst, we are due to become the UK’s first nuclear
site to complete its decommissioning and clean-up programme
- and on the way has delivered the biggest demolition projects
ever undertaken in the UK nuclear industry. Our management
of the final stages of decommissioning offers other sites an
insight into the challenges they will face and provides a
blueprint for success.
STUDSVIK STAND: 34/35
Contact: Amanda Astrop
Unit 14, Princes Park, 4th Avenue,
Team Valley Trading Estate
Gateshead, Tyne and Wear, NE11 0NF
UNITED KINGDOM
Tel: +44 (0) 191 482 1744
Email: sales@studsvik.co.uk
www.studsvik.com
Studsvik offers a range of advanced technical services to the
international nuclear power industry in such areas as waste
52
treatment, decommissioning, engineering & services, and
operating efficiency. <strong>The</strong> company has 60 years experience of
nuclear technology and radiological services. Studsvik is a
leading supplier on a rapidly expanding market.
Studsvik offer specialist services to the international nuclear
power industry in four main areas:
Waste Treatment
• Processing of radioactive waste
• On-site waste services
• Transport logistics
• Waste management consulting services
• Health physics services
Decommissioning
• Decommissioning services
• On-site waste services
Operating Efficiency
• Fuel and Management performance
• Materials integrity and water chemistry
• Nuclear fuel analysis software
• Transport logistics
Service and Maintenance
• Operational and outage support
• Health physics services
• On-site waste services
Studsvik has 1,100 employees in 8 countries and the
company’s shares are listed on the NASDAQ OMX
Stockholm. Following a successful entry into the UK market in
2005, Studsvik have recently developed the Studsvik Metal
Recycling Facility. This is the first new nuclear licensed site to
be brought into operation in the UK in over 20 years. Low
level radioactive waste metal will be processed at the facility
by size reduction and shot-blasting.
TESSELLA STAND: 30
Contact: Shuaib Akhtar
26 <strong>The</strong> Quadrant, Abingdon Science Park, Abingdon
Oxfordshire, OX14 3YS
UNITED KINGDOM
Tel: +44 (0) 1235 555511
Email: info@tessella.com
www.tessella.com
Delivering innovative IT solutions to leaders in the nuclear and
other highly regulated industries
Tessella delivers innovative IT solutions to leaders in the
nuclear industry. Our quality processes consistently achieve
results, and are proven against the demanding regulatory
standards in several sectors. We draw on methods from a
variety of industries to enable our clients to achieve a vast
range of objectives, e.g. condition monitoring based on military
radar techniques enabled improvement in operations and
maintenance at a high level waste processing facility, and work
with UK national archives could preserve the digital legacy of
the industry for future decommissioning requirements. Tessella
has over 28 years of industry experience; starting at UKAEA
Harwell, still a client today.
UKAEA STAND: 33
Contact: <strong>The</strong> Manor Court, Harwell
Oxfordshire, OX11 0RN
UNITED KINGDOM
Tel: +44 (0)1235 431810
Email: info@ukaea.co.uk
www.ukaea.co.uk
UKAEA Ltd has extensive experience in nuclear site
management and operations, decommissioning and waste

management, and technical consultancy. Through projects
spanning the nuclear lifecycle, UKAEA Ltd provides industryleading
technical, design, engineering, safety, and programme /
project management services, both for UK clients and around
the world. Our unrivalled expertise ensures our solutions are
delivered safely, on time and within budget.
UKAEA Ltd’s track record over the years of operating nuclear
sites, fully decommissioning 15 reactors, obtaining over 100
Letters of Compliance, ensuring regulatory compliance and
managing stakeholder relations speaks for itself, as does our
excellent safety record
We work in partnership with our customers, gaining a clear
understanding of their specific requirements, to ensure that we
provide a tailored solution to achieve their unique key
objectives. <strong>The</strong>se fit-for-purpose solutions eliminate
unnecessary expenditure; ensure regulatory compliance and are
delivered safely, on time and to cost.
UNITECH STAND:37
Contact: www.unitech.ws
UniTech Services Group (UniTech) is the nuclear services
subsidiary of UniFirst Corporation. Founded in Springfield,
Massachusetts in 1957, UniTech has grown to more than 500
employees in 11 licensed facilities throughout the United
States, Canada and Europe. UniTech’s management team
features individuals with a diverse range of education, training
and skills. Collectively, UniTech management boasts over 200
years of nuclear/protective wear laundry experience. UniClean,
a division of UniFirst Corporation, is a full service cleanroom
laundry provider specializing in garment rental and processing.
URS CORPORATION STAND: 60/61
PLATINUM SPONSOR
Contact: www.urscorp.com
URS Corporation is a leading provider of engineering,
construction and technical services around the world.
Headquartered in San Francisco, the company operates in 34
countries with approximately 47,000 employees providing
services to federal, state and local governmental agencies as
well as private clients in the Energy, Industrial and
Infrastructure sectors.
<strong>The</strong> Washington Division of URS Corp has particular
expertise in environmental management and operation of
nuclear facilities on behalf of the United States government
and is the market leader in nuclear waste management, disposal
and clean-up.
It has the best overall safety record in the US nuclear industry
and since 1999 has brought this track record and capability to
nuclear waste programmes in the UK.
Washington Division leads the two consortia: UK Nuclear
Waste Management Ltd, and Nuclear Management Partners
Ltd which were successful in winning the management and
operations contracts with the UK Nuclear Decommissioning
Authority for the Low Level Waste Repository and Sellafield
Sites respectively.
VENN ENGINEERING STAND: 18
SERVICES LTD
Contact: Nick Meek
Venn House, Stonehouse Park, Sperry Way
Stonehouse, GL10 3UT
UNITED KINGDOM
Tel: +44 (0)1453 820 170
Email: nick.meek@vennengineering.com
www.vennengineering.com
Venn Engineering Services is a consultancy organisation who
provide support to Nuclear and other industries. Venn were
founded in 2006 and have enjoyed consistent growth ever
since. We have steadily expanded our customer base and have
successfully delivered projects across the UK Nuclear Arena
and in Eastern Europe and Japan. Venn have a commitment to
excellence in everything we do. We can provide our customers
with a level of responsiveness only achievable within a small
company and a depth of knowledge, experience and
underpinning that you would normally expect from a large
organisation.
Venn have capabilities in Decommissioning Planning, Waste
and Decommissioning Strategy Optimisation, Waste and
Decommissioning Technical Development, Project
Development, Project and Programme Management, Site
Inventory Production, Safety Case Support, Environmental
Management Consulting and all aspects of Risk Management.
53

<strong>The</strong> services provided by Venn are deployed as bespoke
consultancy projects and as customer resource enhancement.
Venn are accredited to ISO 9001 Quality and ISO 14001
Environment and are corporate members of the Association for
Project Management APM.
VT GROUP STAND: 3/4
SILVER SPONSOR
Contact: Michael McLoughlin
VT Group
100 Daresbury Park, Warrington,
Cheshire, WA4 4HS
UNITED KINGDOM
Tel: +44 (0) 1928 705000
Email: nuclearservices@vtplc.com
www.vtnuclearservices.co.uk
VT Group is a UK engineering-based support services
company employing more than 12,000 people with turnover of
£1bn. VT’s nuclear business was created through the
acquisition of British Nuclear Group Project Services, a
subsidiary of British Nuclear Fuels plc (BNFL).
As a former BNFL company, VT’s nuclear business has
extensive experience in the international nuclear sector gained
over a 40 year history. With a strong base of highly skilled and
experienced technical and engineering staff that also include
leading experts, VT has an enviable track record of delivering
nuclear clean-up and environmental solutions, particularly
across Western and Eastern Europe including the UK, France
and Bulgaria.
VT’s decommissioning and waste management capabilities are
extensive and include clean-up strategy, project management,
nuclear waste solutions (exempt/VLLW/LLW/ILW)
environmental consulting, sample analysis and waste
characterization.
56
In addition, VT’s radiometric services and instrumentation
capabilities provide a range of specialist services for the
detection and characterization of radioactive material that have
been deployed at many nuclear facilities around the world
including the Europe, USA, China and Japan.
Specific applications include nuclear material assay,
measurement and characterization, waste management and
spent nuclear fuel measurements all using world leading
detection technologies.
WESTINGHOUSE STAND: 63/64
ELECTRIC COMPANY
SILVER SPONSOR
Contact: John Merrell
Westinghouse Electric Company UK Limited.
Unit 5 - Albert Edward House,
<strong>The</strong> Pavillons, Ashton, Preston, PR2 2YB
UNITED KINGDOM
Tel: +44 (0)1772 842 092
Email: Merreljp@westinghouse.com
www.westinghousenuclear.com
Westinghouse Electric Company has a long and distinguished
history in the nuclear industry worldwide. <strong>The</strong> company
provides fuel, services, technology, plant design, and
equipment for the commercial nuclear electric power industry.
Westinghouse provides comprehensive integrated services and
solutions to the D&D and Waste Management industry. We
have acquired extensive experience in the dismantling of
nuclear installations from uranium mill plants to nuclear power
plants. Westinghouse also provides state-of-the art solutions for
the treatment and handling of radioactive waste. Westinghouse
offers proven solutions for the storage of low, intermediate and
high level waste.

WORLEYPARSONS STAND: 56/57
Contact: Mark Liddiard
Earlsgate House, 35 St Ninians Road
Stirling, FK8 2HE
UNITED KINGDOM
Tel: +44 1786 477320
Email: mark.liddiard@worleyparsons.com
www.worleyparsons.com
WorleyParsons is a globally recognised engineering
organisation with significant projects in power (including
nuclear), mining & minerals and oil & hydrocarbons. Our team
is 31,700 strong in 114 offices over 37 countries. We are
recognised for our commitment to health and safety and to the
environment through our HSE Framework OneWay. We
have opened an office in Stirling, Scotland devoted to the
provision of nuclear environmental services to the UK nuclear
industry. This complements the non-nuclear environmental
services offered by our other UK offices in Bristol, Leeds and
London. Polestar GB is a subsidiary of WorleyParsons
specialising in nuclear facility operations, deactivation and
decommissioning, safeguards and security which increases our
range of services to the nuclear decommissioning and new
build sectors.
SELECTED SERVICES
• Environmental radioactivity consultancy
• Conventional and Radioactively contaminated land
characterization and remediation
• Risk assessments and dose assessments
• Radioactive and non-radioactive waste management
• Radiometric surveys including NORM measurement
• Environmental Impact Assessments
• Marine modelling
• Deactivation and Decommissioning
• Radiological engineering and shielding
We also like to thank the following
companies for sponsoring
the following events at the
ICEM’09 <strong>Conference</strong>.
~ Platinum Sponsors ~
BNS NUCLEAR SERVICES
Host of the Golf Simulator
URS CORPORATION
Host of the Monday Luncheon
~ Gold Sponsors ~
AMEC — Host of the Tuesday Luncheon
~ Silver Sponsors ~
CH2M HILL • ENERGYSOLUTIONS
INTERNATIONAL GROUP
NATIONAL NUCLEAR LABORATORY (NNL)
NSG ENVIRONMENTAL
VT GROUP • NUVIA LTD.
WESTINGHOUSE
~ Bronze Sponsor ~
ASSYSTEM ENERGY & NUCLEAR
DEWDROPS • PACTEC
57

Session 1-4 Abstracts
SESSION 1 - OPENING SESSION
ABSTRACTS NOT REQUIRED
SESSION 2A - PANEL: ENVIRONMENTAL CLEANUP WORLDWIDE -
CHALLENGES AND OPPORTUNITIES
ABSTRACTS NOT REQUIRED
SESSION 2B - PANEL: WILL THE LACK OF GEOLOGICAL REPOSITORIES
SLOW THE NUCLEAR RENAISSANCE
ABSTRACTS NOT REQUIRED
SESSION 3 - HOT TOPICS AND EMERGING ISSUES IN D&D
ABSTRACTS NOT REQUIRED
SESSION 4 - NATIONAL PROGRAMS FOR L/ILW
1) UK STRATEGY FOR NUCLEAR INDUSTRY LLW – 16393
Matthew Clark, Joanne Fisher, NDA (UK)
In March 2007 the UK Government and devolved administrations (for Scotland, Wales and Northern Ireland, from here on
referred to as ‘Government’) published their policy for the management of solid low level waste (‘the Policy’). <strong>The</strong> Policy sets out
a number of core principles for the management of low level waste (LLW) and charges the Nuclear Decommissioning Authority
with developing a UK-wide strategy in the case of LLW from nuclear sites. <strong>The</strong> UK Nuclear Industry LLW Strategy has been developed
within the framework of the principles set out in the policy.
A key factor in the development of this strategy has been the strategic partnership the NDA shares with the Low Level Waste
Repository near Drigg (LLWR), who now have a role in developing strategy as well as delivering an optimised waste management
service at the LLWR.
<strong>The</strong> strategy aims to support continued hazard reduction and decommissioning by ensuring uninterrupted capability and
capacity for the management and disposal of LLW in the UK. <strong>The</strong> continued availability of a disposal route for LLW is considered
vital by both the nuclear industry and non-nuclear industry low level waste producers. Given that the UK will generate significantly
more low level waste (~ 3.1 million m3) than there is capacity at the LLWR (~0.75 million m3), developing alternative
effective ways to manage LLW is critical.
<strong>The</strong> waste management hierarchy is central to the strategy, which includes strategic goals at all levels of the hierarchy to
improve its application across the industry.
2) THE ROLE OF THE NATIONAL LOW LEVEL WASTE REPOSITORY OPERATOR IN DELIVERING NEW
SOLUTIONS FOR THE MANAGEMENT OF LOW LEVEL WASTES IN THE UK - 16217
Martin Walkingshaw, LLW Repository Ltd (UK)
<strong>The</strong> UK National Low Level Waste Repository (LLWR) is located near to the village of Drigg in West Cumbria. It is the principal
site for disposal of solid Low Level Radioactive Waste (LLW) in the United Kingdom.
This paper describes the program of work currently being undertaken by the sites operators, (LLW Repository Ltd and its newly
appointed Parent Body Organisation), to extend the life of the LLWR and reduce the overall cost of LLW management to the UK
taxpayer.
<strong>The</strong> current focus of this program is to prevent disposal capacity being taken up at LLWR by waste types which lend themselves
to alternative treatment and/or disposition routes.
<strong>The</strong> chosen approach enables consignors to segregate LLW at source into formats which allow further treatment for volume
reduction or, (for wastes with lower levels of activity), consignment in the future to alternative disposal facilities.
Segregated waste services are incorporated into LLW Disposal commercial agreements between the LLWR operator and waste
consignors.This paper outlines the forward strategy for managing the current and future Low Level Waste (LLW) arisings from the
Sellafield site, including Windscale.
<strong>The</strong> document addresses Sellafield Integrated Waste Strategy (IWS) requirements and reflects changes to the national Low
Level Waste (LLW) policy. <strong>The</strong> underlying driver is that the current estimates of the total volumes of LLW arisings from the Sellafield
site significantly exceed the disposal capacity of the Low Level Waste Repository near Drigg.
3) SELLAFIELD SITE LOW LEVEL WASTE MANAGEMENT STRATEGY - 16234
Laurence Cook, David Loudon, Charles Mason, Sellafield Limited, (UK)
<strong>The</strong> strategy encompasses all current and future low level wastes, including high volume low activity wastes, produced at the
Sellafield site. It derives from detailed consideration of existing management techniques that could be implemented to efficiently
avoid the generation of wastes and to efficiently manage the range of operational and decommissioning wastes that are generated.
It also incorporates the results of a recent stakeholder engagement exercise on Best Practicable Environmental Option Studies for
low level wastes arising on the Sellafield site.
58

Abstracts Session 4
<strong>The</strong> strategy is founded on the Waste Management Hierarchy. It focuses on the avoidance and minimisation of waste, and the
implementation of a range of techniques/approaches to process and dispose of generated waste. <strong>The</strong> strategy does not dictate where
the capability should be developed, rather that it should be developed, in accordance with the national strategy, and should be supported
by business cases and environmental justifications. A phased implementation approach is anticipated, with the ultimate aim
being a suite of capabilities that enable practical, cost-effective application of the WMH. <strong>The</strong> main aspects are
• Increase the focus on waste avoidance
• Further develop the characterisation function
• Develop a sorting and segregation capability
• Develop a thermal treatment capability
• Develop a metal decontamination capability
• Develop a specified landfill capability
• Review the requirement for additional on-site / near site landfill
4) REGULATORY REVIEW OF PRELIMINARY SAFETY ASSESSMENT
FOR THE BAITA BIHOR REPOSITORY, ROMANIA - 16031
Enrique Biurrun, Bernt Haverkamp, DBE Technology GmbH, (Germany);
Klaus-Jürgen Röhlig, Clausthal University of Technology, (Germany)
In the framework of a PHARE project DBE TECHNOLOGY GmbH carried out a regulatory review of the preliminary Safety
Assessment Report for the near surface LILW repository Băiţa-Bihor, Romania.
During the review process several shortcomings of the PSAR from the regulatory point of view were identified. Main findings
concerned shortcomings in regard to the operational safety, especially in the field of mining safety. From the regulatory point of
view, the long-term calculations appeared to lack a sufficient level of conservatism and the necessary clarity and traceability that
would be required to allow a proper evaluation of the concept used for calculating the long-term radionuclide migration and the
particular results of the PSAR.
Respective recommendations were drafted for the Romanian regulator about the changes that should be implemented in the
next version of the PSAR.
Another focus of this project was an investigation on the potential implementation of the Hydraulic Cage Concept for Băiţa-
Bihor. This concept, which originally was developed by DBE TEC for implementation at the Richard Repository, Czech Republic,
helped to decrease the potential future radiological impact for the Richard repository. As the geological situation and the condition
of the waste packages are similar for the two repositories, the Hydraulic Cage Concept or some adaption of itseemed be an obvious
choice to improve the safety of the Băiţa-Bihor repository should that turn out to be necessary. During execution of the project,
it was found that depending on the outcome of the next revised version of the PSAR it seems rather probable that some kind
of measure might be needed to reduce the potential radiological impact. According to the outcome of the project, an adapted simplified
Hydraulic Cage System would be a possible solution to limit the potential future radiological impact.
5) AN OVERVIEW OF US EPAS CURRENT RADIOACTIVE WASTE MANAGEMENT
AND GENERAL RADIATION PROTECTION EFFORTS – 16104
Tom Peake, Loren Setlow, Daniel Schultheisz, Ken Czyscinski, US Environmental Protection Agency, (USA)
<strong>The</strong> United States Environmental Protection Agencys (EPA) Radiation Protection Division is the portion of EPA (or the
Agency) that develops environmental standards for radioactive waste disposal in the United States. One current issue of concern is
the disposal of low activity radioactive waste (LAW), including wastes that would be produced by a radiological dispersal device
(RDD), for which current disposal options may be either inconsistent with the hazard presented by the material or logistically problematic.
Another major issue is related to the resurgence in uranium mining. Over the past several years, demand for uranium for
nuclear power plant fuel has increased as has the price. <strong>The</strong> increase in price has made uranium mining potentially profitable in the
US. EPA is reviewing its relevant regulations, developed primarily in the 1980s, for potential revisions. For example, in-situ leaching
(also known as in-situ recovery) is now the technology of choice where applicable, yet our current environmental standards are
focused on conventional uranium milling. EPA has two actions in process, one related to the Clean Air Act, the other related to
revising the environmental standards that implement the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA). Separately,
but related, EPA has developed over the last several years uranium mining documents that address technologically enhanced
natural occurring radioactive materials (TENORM) from abandoned uranium mines, and wastes generated by active uranium
extraction facilities.
Lastly, in 1977 EPA developed environmental standards that address nuclear energy, fuel fabrication, reprocessing, and other
aspects of the uranium fuel cycle. In light of the increased interest in nuclear power and the potential implementation of advanced
fuel cycle technologies, the Agency is now reviewing the standards to determine their continued applicability for the twenty-first
century.
6) ANALYSIS OF MANAGEMENT AND DISPOSAL ALTERNATIVES FOR
LOW ACTIVITY RADIOACTIVE WASTE – 16192
Keith Anderson, ECC (USA)
U.S. Government and Private decommissioning and remediation activities at nuclear sites and facilities often generate in large
volumes and mass radioactive waste that is of low activity. In large part, the low activity radioactive waste generated from decommissioning
and remediation activities are below regulatory limits for low level radioactive waste, while not meeting site specific
dose and risk-based cleanup criteria. Policies and strategies for the remediation, management, and disposal of low activity radioactive
waste in these circumstances often explore alternative options to fully licensed disposal. Primary goals in exploring alternative
disposal options are protection of the public and the environment, while achieve a cost-effective solution. Vague regulations and
arbitrary interpretation by federal and state regulators may enhance alternative disposal options or quash efforts by those conduct-
59

Session 4-5 Abstracts
ing the remediation and decommissioning. Fundamental to the issues is the overriding concern of a lack of clarity and increased
liability in the regulatory structure of the grey area that is low activity radioactive wastes. This paper explores the current efforts
by the United States and <strong>International</strong> regulatory community to better define low activity radioactive waste and to provide effective
and protective waste management and disposal policies and strategies.
7) STRATEGY AND PRACTICE IN SPENT SEALED SOURCES MANAGEMENT IN BELGIUM - 16335
Vincent De pooter, NIRAS/ONDRAF (Belgium);
Marnix Braeckeveldt, David Vanleeuw, Gunter Van Zaelen, NIRAS/ONDRAF (Belgium)
Radioactive sources are used for a variety of purposes, e.g. in medical treatment and diagnosis, research applications, measurement,
testing, detection and calibration in industry, educational activities in colleges and universities etc. As part of its mission,
ONDRAF/NIRAS, the Belgian Radioactive Waste Management Agency, draws up an inventory of all radioactive substances and
nuclear installations on the Belgian territory. In recent years this inventory has been used to launch specific campaigns for the collection
of different types of radioactive sources. In addition to this, the Royal Decree of 23 May 2006 concerning the transposition
into Belgian law of the Spent High Activity Sealed Sources and the Management of Orphan Sources Directive of the EU
(2003/122/EURATOM) has led to an increase in the number of requests addressed to ONDRAF/NIRAS for the collection of these
types of radioactive waste and to an intensified collaboration between ONDRAF/NIRAS and the Belgian Safety Authority
FANC/AFCN towards an effective management of orphan sources. Specific properties of these spent sources such as their activity,
external dose rate, weight, size and/or their invalid special form certificate may complicate the transport and final treatment and
conditioning of this type of waste and that is why these operations require careful attention. An overview of the radioactive sources
already collected as radioactive waste or still present in the nuclear installations, different cases and problems encountered are presented
in this paper, as well as the waste management options adopted by ONDRAF/NIRAS to deal with this type of waste.
8) IMPROVEMENT OF THE MANAGEMENT OF INSTITUTIONAL
RADIOACTIVE WASTE IN SLOVENIA – 16092
Marija Fabjan, Agency for Radwaste Management, SI-1000 (Slovenia);
Jože Rojc, RŽV- Mine Žrovski vrh, (Slovenia); Koen Lenie, Leniko, (Belgium); Yves Niels, IRE, (Belgium);
GasperTavar, Matjaž Stepišnik, Institut “Jožef Stefan” (Slovenia)
<strong>The</strong> Central Storage Facility (CSF) in Brinje is the only storage facility for institutional radioactive waste in Slovenia.
<strong>The</strong> storage has been in operation since 1986. Since the year 1999, operation of the CSF in Brinje and managing of institutional
radioactive waste in Slovenia has been under the control of Agency for Radwaste Management (ARAO).
At the time of taking over the CSF, the waste in store was not fully characterised and in some cases the available data did not
match records and inventories. Besides this, some shielded containers and drums were degraded, which creates a potential risk of
uncontrolled spread of contamination.
In addition, in 1999 the Slovene Nuclear Safety Administration (SNSA) requested the ARAO to perform refurbishing works
in the CSF in order to reinforce and tighten the building on the one hand, and characterise and condition radioactive waste in store
on the other.
In order to improve the existing situation ARAO lunched considerable assistance and know-how transfer through training and
other technical cooperation within the IAEA and the EC projects.
In this context, several projects have been carried out in the period between 1999 and 2007.
However, these projects only addresses one third of the total inventory of radioactive waste.
In particular, the radioactive waste in the form of bulky material, which occupies a significant surface of the CSF, will not be
processed.
SESSION 5 - LLW CHARACTERIZATION, TREATMENT & PACKAGING DEVELOPMENTS - PART 1 OF 2
1) TREATMENT OF IRRADIATED CORE COMPONENTS FROM BWR
AND PWR NUCLEAR POWER PLANTS - 16043
Joerg Viermann, Joerg Radzuweit, Andreas Friske, GNS Gesellschaft fuer Nuklear-Service mbH (Germany)
During Operation of Nuclear Power Plants Components inside the reactor core are exposed to neutron radiation. Removable
Components like control rods, flow restrictor assemblies or water channels are replaced from time to time to prevent a higher activation.
<strong>The</strong>se components are then stored in the fuel pond.
For disposal the components have to be cut to size in order to fit into flasks or containers suitable for a repository. For cutting
of core components GNS operates different under water shears, one of them a combination with a 700 tonnes compactor. Over a
period of more than 20 years core components have been treated at a number of NPP (PWR as well as BWR). Since 1996 GNS has
also been operating a hot cell facility for treatment of irradiated core components as a joint venture with the Research Centre Karlsruhe.
<strong>The</strong> presentation will give an overview of the different facilities, describe the processes, experiences and lessons learned.
2) CHARACTERIZATION OF NORM SOURCES IN PETROLEUM COKE CALCINING PROCESSES - 16314
Ian Hamilton, Donald Halter, Matthew Arno, Foxfire Scientific (USA); Robert Berry, Foxfire Scientific, Inc. (UK)
Petroleum coke, or “petcoke,” is a waste by-product of the oil refining industry. <strong>The</strong> majority of petcoke consumption is in
energy applications; catalyst coke is used as refinery fuel, anode coke for electricity conduction, and marketable coke for heating
cement kilns. Roskill has predicted that long-term growth in petroleum coke production will be maintained, and may continue to
increase slightly through 2012.
Petcoke must first be calcined to drive off any undesirable petroleum by-products that would shorten the coke productlife cycle.
As an example, the calcining process can take place in large, rotary kilns heated to maximum temperatures as high as approximately
1400-1540°C. <strong>The</strong> kilns and combustion/settling chambers, as well as some cooler units, are insulated with refractory bricks and
other, interstitial materials, e.g., castable refractory materials, to improve the efficiency of the calcining process. <strong>The</strong> bricks are typ-
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Abstracts Session 5-6
ically made of 70-85-percent bauxite, and are slowly worn away by the calcining process; bricks used to line the combustion chambers
wear away, as well, but at a slower rate. It has been recognized that the refractory materials contain slight amounts of naturally
occurring radioactive materials (NORM) from the uranium- and thorium-decay series. Similarly, low levels of NORM could be
present in the petcoke feed stock given the nature of its origin.
3) MEASUREMENT OF SOLID-LIQUID MIXTURES USING ELECTRICAL TOMOGRAPHY
MEASUREMENT TECHNIQUES - 16088
Gary Bolton, Industrial Tomography Systems (UK); StevenStanley, National Nuclear Labpratory (UK)
Electrical Impedance Tomography measurement techniques have been applied to a variety of solid-liquid processes in the laboratory
and on industrial plant. This paper reviews the advances in the measurement techniques to determine key process information
in solid-liquid systems such as concentration mapping, mixture homogeneity, interface detection and suspension velocity.
A number of applications to solid-liquid flow applications are presented. <strong>The</strong> use of the technology for improved design and
operation is highlighted, as are the opportunities for on-line sensing for flow measurement, fault detection and process control. A
recent development in high-speed electrical imaging has allowed velocity maps to be calculated for fast flowing suspensions (up
to 10 ms-1).
<strong>The</strong> methodology for determining mixture homogeneity in both pipeline flows and agitated tanks are summarised. Finally the
application of a linear ERT electrode array to identify interfaces during the settling of solid-liquid mixtures is presented.
SESSION 6 - LLW CHARACTERIZATION, TREATMENT & PACKAGING DEVELOPMENTS - PART 2 OF 2
1) INCREASING OPERATIONAL EFFICIENCY IN A RADIOACTIVE WASTE PROCESSING PLANT - 16100
Tom Turner, Stuart Watson, UKAEA (UK)
<strong>The</strong> solid waste plant at Harwell in Oxfordshire, contains a purpose built facility to input, assay, visually inspect and sort
remote handled intermediate level radioactive waste (RHILW). <strong>The</strong> facility includes a suite of remote handling cells, known as the
head-end cells (HEC), which waste must pass through in order to be repackaged. Some newly created waste from decommissioning
works on site passes through the cells, but the vast majority of waste for processing is historical waste, stored in below ground
tube stores. Existing containers are not suitable for long term storage, many are already badly corroded, so the waste must be efficiently
processed and repackaged in order to achieve passive safety.
<strong>The</strong> Harwell site is currently being decommissioned and the land is being restored. <strong>The</strong> site is being progressively delicensed,
and redeveloped as a business park, which can only be completed when all the nuclear liabilities have been removed. <strong>The</strong> recovery
and processing of old waste in the solid waste plant is a key project linked to delicensing of a section of the site. Increasing the
operational efficiency of the waste processing plant could shorten the time needed to clear the site and has the potential to save
money for the Nuclear Decommissioning Authority (NDA).
2) MANAGEMENT OF HISTORICAL RADIOACTIVE WASTE - 16267
Gheorghe Dograu, Felicia Dragolici, Laura Ionascu, GheorgheRotarescu, National Institute
of Reserch & Development for Physics and Nuclear Engineering-Horia Hulubei (Romania)
<strong>The</strong> development of the nuclear techniques in Romania and the commissioning of the WWR-S research reactor belonging to
the Institute of Physics and Nuclear Engineering -(NIPNE) demand to deal with the storage and disposal of radioactive waste. <strong>The</strong>
institute decided to store the radioactive waste inside a building that belonged to the Defense of Capital City System named Fortwhich
is located on the Magurele site. About 5000 packages were produced and transferred to the storage facility of radioactive
waste treatment plant after decommissioning of Fort building. In the mean time a repository was commissioned and the most part
of the waste has been disposed. <strong>The</strong>re still were remained about 800 packages which, in time, became corroded. A huge effort was
put in place in order to repack the waste for disposal. At the end of 2008, the whole amount of historical waste have been treated,
and disposed or stored.
<strong>The</strong> paper describes the management of historical radioactive waste from the storage facility of Radioactive Waste Treatment
Plant.
3) VOLUME REDUCTION OF RADIOACTIVE CONCRETE WASTES GENERATED
BY DISMANTLING NUCLEAR FACILITIES - 16165
Byung youn Min, Wang-Kyu Choi, Jung-Woo Park, Kune-Woo Lee, Korea Atomic Energy Research Institute, (Korea)
In Korea, the decontamination and decommissioning of the retired research reactors (KRR-1&2) and a uranium conversion
plant (UCP) at Korea Atomic Energy Research Institute (KAERI) has already been under way. Hundreds of tons of concrete wastes
are produced from these facilities. <strong>The</strong> recycle or the volume reduction of the contaminated concrete wastes through the application
of appropriate treatment technologies have the merit from the view point of the increase in resource recycling as well as the
decrease in the amount of wastes to be disposed resulting the reduction of disposal cost and the enhancement of disposal safety. It
is well known that most of the radionuclide is concentrated on the one of the concrete constituents, a porous hydrated cement matrix
and the radionuclide can be easily removed from the concrete wastes by separating cement matrix which can be done by heating to
weaken the adherence force between the cement matrix and the aggregates followed by mechanical crushing and milling processes.
<strong>The</strong>refore, KAERI has developed the volume reduction technology applicable to an activated heavy concrete waste generated
by dismantling KRR-2 and a uranium contaminated light concrete produced from a UCP, which can separate relatively clean aggregates
from the dismantled concrete wastes contaminated with α and β-γ emitters. <strong>The</strong> separation of radioactive constituents from
contaminated concrete waste carried out by heating and mechanical crushing and milling with the light and heavy concrete to establish
the volume reduction process for the concrete wastes generated by dismantling nuclear facilities. <strong>The</strong> volume reduction rate
could be obtained above 70% for the heavy weight concrete waste from the KRR-2 and above 80% for the light weight concrete
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Session 7 Abstracts
waste from the UCP. Also, we investigate the characteristics of chemical leaching for removal of radionuclide from the fine cement
powder as a radioactive waste produced during the course of the mechanical crushing and milling to minimize the final radioactive
waste volume for disposal. Chemical leaching of the radioactive fine cement powder was effective in HNO 3 solution. <strong>The</strong> removal
efficiency for the fine cement powder contaminated with uranium compound was achieved by up to 97%.
SESSION 7 - NATIONAL AND INTERNATIONAL ER PROGRAMS
1) EXPECTATIONS FOR MANAGING CONTAMINATED GROUND AND GROUNDWATER:
DEVELOPING A COMMON VIEW OF NDA AND REGULATORS - 16252
Anna Clark, NuclearDecommissioning Authority (UK)
<strong>The</strong> management of contaminated ground and groundwater is a notable contributor to the challenge we face in cleaning up the
legacy of the UKs civil nuclear industry in a safe, cost-effective and environmentally responsible manner. To facilitate this mission,
the Nuclear Decommissioning Authority and Regulators have elected to try and document our common expectations for the management
of contaminated ground and groundwater arising on and extending off nuclear licensed sites in the UK.
<strong>The</strong> aims are to:
• speak in one voice about land quality management, both outlining our common expectations and explaining any differing
expectations where consensus is difficult;
• act as the glue between existing NDA and regulatory principles and legislation;
• interpret principles to ensure they are unambiguous and implementable, therefore facilitating forward planning of programmes
and deliverables;
• clarify practical and strategic links between land quality management and related topics such as waste management and
site end states, including delicensing;
• provide a framework for dialogue against which progress in land quality management can be mapped; and,
• promote positive action to deliver hazard reduction in a proportionate and sustainable manner.
To achieve the above aims, this paper outlines the development of our common view on the optimum approach to issues such
as the control of contaminated ground and groundwater, justifying implementation or deferral of land remediation, and defining
intervention and remediation standards.
2) THE GOVERNMENT OF CANADA’S PROGRAMMES FOR RADIOACTIVE WASTE
CLEANUP AND LONG-TERM MANAGEMENT - 16133
David McCauley, Doug Metcalfe, Marcia Blanchette, TomCalvert, Natural Resources Canada (Canada)
<strong>The</strong> Government of Canada’s 1986 Policy Framework for Radioactive Waste Management establishes that waste owners are
responsible for the management of their radioactive wastes. This includes the planning, funding, and implementation of long-term
waste management initiatives. Within this context, the Government has established three separate programmes aimed at addressing
the long-term management of radioactive wastes for which it has accepted responsibility.
<strong>The</strong> largest of these programs is the Nuclear Legacy Liabilities Program (NLLP). <strong>The</strong> objective of the NLLP is to address certain
radioactive waste and decommissioning liabilities resulting from 60 years of nuclear research and development at Atomic Energy
of Canada Limited sites in Canada. In 2005, the Government recognized this liability in its Public Accounts and, in 2006, it initiated
the first $520 million 5-year work plan of what is expected to be a 70-year strategy. <strong>The</strong> costs of implementing the full strategy
are estimated at $6.8 billion (2005$).
Canada’s Historic Waste Program is a second program that is designed to address low-level radioactive wastes across Canada
that are not managed in an appropriate manner for the long-term and for which the current owner can not be held responsible. <strong>The</strong>se
wastes mainly emanate from the 1930’s and the very early days of nuclear industry in Canada when radioactive ores were mined
and transported long distances for processing. While the Historic Waste Program has been in place since 1982, the Government of
Canada launched the Port Hope Area Initiative in 2001 to deal with the bulk of this environmental problem.
3) EUROPEAN RADIATION SURVEY AND SITE EXECUTION MANUAL (EURSSEM) - 16176
(Switzerland); Lucien Tuenckens, Colenco Power Engineering Ltd.(Switzerland) Marek Vasko, Decom, a.s. (Slovakia);
Kristina Kristofova, Decom a.s.(Slovakia) Igor Matejovic, Eva Hajkova,DECOM, a.s.(Slovakia) Vladimir Daniska,
Deconta, a.s.(Slovakia)
Within the framework of the “Co-ordination Network on Decommissioning of Nuclear Installations Project (2005- 2008)”
funded by the European Community a first edition of EURSSEM has been developed to promote common understanding of key
issues in the development of a strategy, implementation and execution of a programme to remediate radioactively contaminated
sites.
<strong>The</strong> objective of EURSSEM is to describe and provide a consistent consensus information and guidance on strategy, planning,
implementation and execution of stakeholder involvement, performing, and assessing radiological soil surface and groundwater
(final) status surveys to meet established dose- or risk-based release criteria, and/or remediation, restoration, reuse and stewardship
objectives, while at the same time encouraging effective use of human, raw material and financial resources.
To be able to provide a consistent guidance and leading practices to involved participants (stakeholders) in a remediation programme
for radioactively contaminated sites, an extensive literature study has been performed to collect important documents that
have been produced in this field by the <strong>International</strong> Atomic Energy Agency (IAEA), the SAFEGROUNDS Learning Network,
Multi- Agency Radiation Survey and Site Investigation Manual (MARSSIM) and other national and international institutes.
EURSSEM incorporates information provided in those and other documents to conduct all actions at radioactively ted and potentially
radioactively contaminated sites and/or groundwater up to their release for restricted or unrestricted (re)use.
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Abstracts Session 7-8
Brief descriptions are provided about the background and the need for a document like EURSSEM, about key issues like
stakeholder involvement and archiving for future referencing including the follow-up of the further development of EURSSEM.
4) IAEA - ENVIRONET: THE NETWORK ON ENVIRONMENTAL MANAGEMENT AND REMEDIATION - 16421
Horst Monken-Fernandee, IAEA (AUSTRIA, Decommissioning Authority, (UK)
Over the past decade, a number of remediation methods have been developed worldwide to deal with the environmental cleanup
of radiologically contaminated sites. <strong>The</strong>y vary in terms of sophistication and costs and must be selected on a case-by-case basis.
However, the development of a successful remediation programme does not only rely on the availability of technology and expertise.
Good management plans are needed. Ultimately, planning is an essential component of the overall business and all the steps
need to be articulated in a reasonable way to avoid waste of time and resources. Countries that had to deal with extensive remediation
work have been able to test various approaches resulting in the selection of adequate strategies for remediation. As a consequence,
they are holders of expertise and know-how which may be useful and applicable to other countries that need to implement
remediation programmes. However, quite often, the implementation of a safe and economic approach consistent with good international
practice may be hindered by constrained human and financial resources and scarce expertise in environmental remediation.
Developing countries face specific challenges to implement remediation projects, not only because of the lack of resources
but also because of the lack of appropriate technology and expertise and these things can end-up constituting important barriers for
project implementation. Experience has shown that with appropriate planning and assistance remedial actions are more likely to be
implemented. As such the interaction of inexperienced with experienced countries facilitated by the IAEA may lead to better conditions
for real implementation of projects and lessons learned with this relationship may inspire countries to reproduce (after necessary
adaptation to local conditions and constraints) the experience gained by others. However, the benefits of networking may
not be restricted to the support of developing Member States. More developed Member States can also benefit from networking as
they will have an open and flexible environment to exchange experience and build up partnerships.
SESSION 8 - EXPERIENCES IN ER CLEAN-UP ACTIONS
1) SAFE AND COMPLIANT MANAGEMENT APPROACH TO ENVIRONMENTAL REMEDIATION
OF THE HANFORD SITE CENTRAL PLATEAU - 16025
John Lehew, CH2M HILL Plateau Remediation Company (USA)
CH2M HILL Plateau Remediation Company (CHPRC) is the U.S. Department of Energys (DOE) contractor responsible for
the safe, environmental cleanup of the Hanford Sites Central Plateau.
<strong>The</strong> 586-square-mile Hanford Site is located along the Columbia River in southeastern Washington State, U.S.A. A plutonium
production complex, housing the largest volume of radioactive and contaminated waste in the nation, with nine nuclear reactors and
associated processing facilities, Hanford played a pivotal role in the nation’s defense for more than 40 years, beginning in the 1940s
with the Manhattan Project. Today, under the direction of the DOE, Hanford is engaged in the world’s largest environmental cleanup
project.
<strong>The</strong> Plateau Remediation Contract is a 10-year project paving the way for closure of the Hanford Site through remediation of
over 700 waste sites, burial grounds, and groundwater systems; deactivation, decommission, decontamination, and demolition (D4)
activities of over 400 site buildings; treatment of sludge; and disposition of transuranic waste (TRU), spent nuclear material containers,
spent nuclear fuel, and reactors.
<strong>The</strong> $4.5 billion project, funded through the U.S. DOE Office of Environmental Management, focuses equally on reducing
risks to workers, the public, and the environment and on protecting the Columbia River. Specifically, CHPRCs scope includes:
• 100K Area remediation, sludge treatment, and reactor interim safe storage
• Plutonium Finishing Plant Closure
• Groundwater/vadose zone remediation
• Groundwater, soil, and facility regulatory decision/other documents
• Facility, waste site, and canyon remediation
• Waste retrieval, treatment and disposal, and fuels management
• Fast Flux Test Facility near-term shutdown activities
• Facility and waste site minimum-safe/surveillance and maintenance (S&M).
2) REMEDIATION OF THE SITE OF A FORMER ACTIVE HANDLING BUILDING
IN THE UNITED KINGDOM - 16041
Limited (UK); Andy Staples, United Kingdom Atomic EnergyAuthority (UK)
In 2000, Nuvia Limited was contracted to carry out the decommissioning of a former Active Handling Building A59 on the
United Kingdom Atomic Energy Authority (UKAEA) site at Winfrith. This is in support of UKAEA’s mission, which is to carry
out environmental restoration of its nuclear sites and to put them to alternative uses wherever possible. Recently UKAEA has been
reorganised and responsibility for the site lies with Research Sites Restoration Limited (RSRL) with funding provided by the
National Decommissioning Authority (NDA).
Following major decommissioning operations the main containment building structure and the two suites of concrete shielded
caves were demolished between June 2006 and March 2007 leaving just the base slab for final removal and the site remediation
operations undertaken. <strong>The</strong> base slab contained a quantity of encast, internally contaminated items including more than 100 steel
mortuary tubes set up to 6.6m deep into the slab. At the outset it was suspected that some leakage of radioactive contamination had
occurred into the ground although the precise location/s of the leakage was unknown. As a result the scope of the work required
the underlying soil to be carefully monitored for the presence of radioactive contamination and, if detected, its remediation to an
end state suitable for un-restricted use without planning or nuclear regulatory controls.
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Session 8-9 Abstracts
3) A SUCCESSFUL REMEDIATION PROJECT - 16400
L. Max Scott, Louisiana State University (USA)
As part of a program to visit formerly licensed sites to determine if they meet current uncontrolled release conditions, a United
States Nuclear Regulatory Commission (USNRC) inspection was conducted in the fall of 1993 at a site that had possessed a
radioactive material license from about 1955 to 1970. While the license was in force, the plant processed magnesium scrap containing
up to 4 percent thorium. <strong>The</strong> source of the scrap is believed to be the aircraft manufacturing industry. <strong>The</strong> scrap was placed
in furnaces and heated to the melting point of magnesium, and the molten magnesium was drawn off, leaving the thorium with the
residue (dross). Under the regulation in existence at that time, the thorium dross was buried on site in an approximate 14 acre field.
In 1993 the inspector found readings up to 900uR/h.
Early in 1994 an informal grid survey of most of the 14 acre site was conducted. Based on that survey, it was concluded that
the thorium was widespread and extended beyond the property lines. <strong>The</strong> preliminary findings were reported to the USNRC, and
in 1994 the site was designated as a Site Decommissioning Management Plan (SMPD) site. A remediation team was formed which
included the following disciplines: remediation health physics, geology, hydrology, engineering, law, public relations, and project
management. This remediation team planned, participated in selecting vendors, and provided project over site for all activities from
site characterization through the final status survey. In 2006 the site was released for uncontrolled access.
A chronology of activities with lessons learned will be presented.
4) EVALUATION AND POTENTIAL REMEDIATION OF THE INDUSTRIAL
NORM LEGACY IN LIVERPOOL - 16096
Nigel Reeves, Gordon John, Bob Major, AMEC Nuclear Ltd.(UK)
Sefton, on the north side of Liverpool, holds a radioactive legacy from its industrial past. This legacy is in the form of Tin slag
buried in sub-surface seams. Located near the docks and adjacent to the rich Lancashire coal seams, Sefton became one of the main
production centres of Tin plate in Britain. A consequence of this industrial process is the production of mildly radioactive waste
slag.
Tin rich ores are heated under reducing conditions to produce a molten metal stream This is then separated into the component
metal streams. Solid wastes produced by this process are known as slag and were usually stored on site in spoil heaps. Because this
slag is a very hard, glassy material it has been historically used as aggregate in underlying roads and rail way sleepers. Many of
these sites pre-date the introduction of the regulation of radioactive substances in the UK and have never been under legislative
control under the Radioactive Substances Act, RSA93. <strong>The</strong>re is a risk that the existence may not be known of some of these sites.
U-238 and Th-232 and their associated decay chains, are the major contributors to the radionuclide inventory of the slags, levels
of these radionuclides being in the range 1-10Bq/g. A series of alpha and beta decays for both chains leads eventually to the
generation of a stable isotope of lead. Radiologically, the main area of concern is with the potential inhalation or ingestion of contaminated
dusts. <strong>The</strong>re is also a potential for Ra-226 to leach out into groundwater.
SESSION 9 - NATIONAL, MULTI-NATIONAL AND INTERNATIONAL
1) THE NUCLEAR ENGINEERING DOCTORATE AND NTEC CPD & MASTERS PROGRAMMES: EDUCATION,
TRAINING AND RESEARCH FOR THE DECOMMISSIONING SKILLSBASE - 16395
John W. Roberts, University of Manchester (UK)
Since its establishment in 2005 the Nuclear Decommissioning Authority has a remit to maintain the skillsbase for safe, secure
and cost effective decommissioning of the existing UK civil nuclear power plants and associated facilities. With an aging workforce
and a competitive tender process for each project a number of new companies are realising the potential of the UK decommissioning
market.
<strong>The</strong> Nuclear Engineering Doctorate and NTEC Masters Programmes have been designed to provide the nuclear workforce of
the future. <strong>The</strong> doctorate is a partnership between industry, a university partner and the research engineer with the benefit to industry
that the research engineer is based with the industrial partner. Technical and management modules are studied at the university
whilst the research project is carried out in the industrial environment.
<strong>The</strong> Masters programme draws on the expertise of 11 Higher Education Institutes and offers over 20 modules that are delivered
in a short-fat format either as stand alone CPD courses or, by taking further modules, a certificate, diploma or on completion
of a research project an M.Sc. Modules are available that cover the technical aspects of decommissioning as well as management
of the decommissioning process. <strong>The</strong> availability of modules in a Distance Learning format now enables students based around the
world to benefit from this programme.
This paper will describe the two programmes in detail and provide examples of current projects that are delivering the research
and workforce required for a successful decommissioning programme.
2) COLLABORATIVE RETEK EXCHANGE — AN INNOVATIVE SOLUTION TO THE SKILLS
AND RESOURCE SHORTAGE IN THE NUCLEAR INDUSTRY - 16396
Corhyn Parr, Retek Consulting (UK)
A Different Approach to the Skills and Resource Shortage. <strong>The</strong> Nuclear Industry has for many years been concerned about a
skills and resource shortage. This has been due to a poor perception of the industry by those on the outside, highly competitive
industries vying for the same resource pool, a steep retirement curve for highly qualified staff and a lack of graduates entering
industry.
Here in the UK the creation of the National Skill Academy for Nuclear (NSAN) has put in place a framework to record skills
and look to accredit the training providers in the nuclear industry to ensure that the correct skills for the future are available. This
has gone some way to solving the skills problem and developing a well recognised accredited system but what about resource where
are the additional qualified resources going to be found?
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Abstracts Session 9
3) SHARED, REGIONAL REPOSITORIES: DEVELOPING A PRACTICAL IMPLEMENTATION STRATEGY - 16310
Ewoud Verhoef, COVRA (Netherlands) Charles McCombie,Neil A. Chapman, Arius Association (Switzerland)
<strong>The</strong> basic concept within both EC funded SAPIERR I and SAPIERR II projects (FP6) is that of one or more geological repositories
developed in collaboration by two or more European countries to accept spent nuclear fuel, vitrified high-level waste and
other long-lived radioactive waste from those partner countries. <strong>The</strong> SAPIERR II project (Strategic Action Plan for Implementation
of Regional European Repositories) examines in detail issues that directly influence the practicability and acceptability of such
facilities. This paper describes the work in the SAPIERR II project (2006-2008) on the development of a possible practical implementation
strategy for shared, regional repositories in Europe and lays out the first steps in implementing that strategy.
4) UK SURPLUS SOURCE DISPOSAL PROGRAMME - 16097
Nigel Reeves, Gordon John, AMEC (UK)
<strong>The</strong> UK Surplus Source Disposal Programme (SSDP), managed by the Environment Agency, was designed to remove redundant
radioactive sources from the public domain. <strong>The</strong> UK Government Department for Environment, Food and Rural Affairs
(Defra) was concerned that disused sources were being retained by hospitals, universities and businesses, posing a risk to public
health and the environment.
AMEC provided a range of technical and administrative services to support the SSDP. A questionnaire was issued to registered
source holders and the submitted returns compiled to assess the scale of the project. A member of AMEC staff was seconded to the
Environment Agency to provide technical support and liaise directly with source holders during funding applications, which would
cover disposal costs.
Funding for disposal of different sources was partially based on a sliding scale of risk as determined by the IAEA hazard categorisation
system. This funding was also sector dependent.
5) GEOLOGICAL SITING REGIONS PROPOSED BY NAGRA FOR THE L/ILW AND THE HLW
REPOSITORIES AS THE FIRST STEP IN THE APPLICATION OF THE RECENTLY
ESTABLISHED SWISS SITE SELECTION PLAN - 16295
Jürg W. Schneider, Andreas Gautschi, Piet Zuidema, Nagra(Switzerland)
In Switzerland, the Nuclear Energy Law requires the disposal of all radioactive waste in deep geological repositories. <strong>The</strong>
Swiss programme foresees two types of repositories for this purpose: a low- and intermediate-level waste (L/ILW) and a high-level
waste (HLW) repository. <strong>The</strong> necessary scientific and technical work preparing for deep geological disposal is well advanced and
the feasibility of geological repositories that provide the required long-term safety has been successfully demonstrated for all waste
types arising in Switzerland. <strong>The</strong>se feasibility demonstrations have been approved by the Swiss Government (the Federal Council).
Sufficient knowledge is available to allow the next steps in the selection of repository sites to be defined. <strong>The</strong> legal framework is
also in place and organisational measures have been provided that will allow the tasks to be performed in the coming years to be
implemented efficiently. <strong>The</strong> concept part of the so-called Sectoral Plan Deep Geological Repositories (i.e. the rules for repository
siting) that was issued by the Federal Council on 2nd April 2008 plays a major role, as it regulates the details of the site selection
process to be conducted over the next years. <strong>The</strong> Sectoral Plan specifies that selection of geological siting regions and sites for
repositories in Switzerland will be conducted in three stages. Stage 1 ends with the proposal of geological siting regions within
which the repository projects will be elaborated in more detail in the later stages of the Sectoral Plan (stages 2 and 3); stage 3 will
comprise field investigations (boreholes, 3D reflection seismic surveys). <strong>The</strong> final step will be the identification of a L/ILW and a
HLW site for which general licences will be requested.
6) A SUMMARY OF RADIOLOGICAL WASTE DISPOSAL PRACTICES
IN THE UNITED STATES AND THE UNITED KINGDOM - 16379
Victoria Maranville, AMEC Earth and Envorinmental (USA);Richard McGrath, AMEC Nuclear (UK)
A systematic review of near-surface repositories for radioactive waste in the United States (US) was conducted. <strong>The</strong> main focus
of the review consisted of a literature search of available documents and other published sources on low level radioactive waste
(LLRW) disposal practices, remediation of LLRW sites in the US, and public participation for remediation efforts of near-surface
radiological waste disposal sites in the US. This review was undertaken to provide background information in support of work by
the UK’s Low Level Waste Repository (LLWR) and to aid in optimizing the future management of this site.
<strong>The</strong> review contained a summary of the US and United Kingdom (UK) radiological waste classification requirements including
a discussion of the waste types, disposal requirements, and the differences between US and UK disposal practices.
A review of the regulatory process and evolution of regulatory requirements in the US is presented. <strong>The</strong> UK regulatory environment
is also discussed and contrasted to the US process. <strong>The</strong> public participation, as part of the US regulatory process, is also
provided and the mechanism for stakeholder identification and involvement is detailed.
In an attempt to demonstrate how remediation of radiologically impacted sites is implemented in the US, existing US case studies,
in which remediation activities were carried out, were reviewed. <strong>The</strong> following information was compiled: type of wastes disposed
of to US shallow ground facilities [with comparison with UK classifications], facility designs (with special emphasis on those
directly comparable to the subsurface conditions in the UK), and deficiencies identified in operation or in demonstrating safe post
closure; and processes and difficulties in remedial actions encountered at the selected sites. Stakeholder involvement is also discussed
within the case studies.
Publicly available information related to radiological waste management and disposal practices were reviewed. Two sites are
presented in this publication for discussion. <strong>The</strong>se US sites were selected based on the site similarities to conditions in the UK.
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Session 9-10 Abstracts
7) IMPLEMENTATION OF THE BEST IN CLASS PROJECT MANAGEMENT AND CONTRACT MANAGEMENT
INITIATIVE AT THE DEPARTMENT OF ENERGYS OFFICE OF ENVIRONMENTAL MANAGEMENT - 16062
Scott Van Camp, U.S. Dept. of Energy (USA); Mike Deiters,Project Time & Cost, Inc. (USA)
Since its creation in 1989, the Department of Energy (DOE), Office of Environmental Management (EM) has struggled with
a legacy of inadequate project management and contract management. This has been manifested in recurring scope changes, cost
overruns and schedule delays, and has been documented in multiple internal and external reviews. EM has committed itself to
improving project performance and undertaken a number of proactive management initiatives including the development of a Best
in ClassProject Management and Contract Management organization (i.e., the BICPM Initiative).
During 2007, EM assessed the status of project management and contract management at 15 EM sites. <strong>The</strong>se assessments evaluated
strengths and weaknesses in 12 key project management capabilities and three contract management benchmarks. <strong>The</strong> January
2008 Compilation Assessment Report showed that EM faces significant challenges in its mission execution due to staffing
shortages, project and contract management integration, insufficient project-oriented culture, and lack of a clear role for Headquarters
in BICPM.
EM then formulated a strategy to meet their objectives in the March 2008 Corporate Implementation Plan. It summarizes
BICPM efforts, introduces the vision for BICPM, identifies the strategy for achieving BICPM, and describes a process for implementing
BICPM. That is, it acts as a roadmap to address EMs challenges. It also documents 18 Recommended Priority Actions
(RPAs) that are the key to correcting these challenges. <strong>The</strong>se RPAs provide a clear path forward that can be communicated to the
entire EM organization and provide the foundation upon which a BICPM culture can be built. EM has since gained considerable
momentum and progress towards institutionalizing BICPM. This paper provides a discussion of the BICPM Initiative and its implementation.
8) EDUCATION AND INDUSTRY PARTNERSHIP: A CASE STUDY OF CO-DELIVERY - 16065
Timothy Mercer, John Tyndall Institute for Nuclear Research (UK);
Jonathan Francis, University of Central Lancashire (UK)
One of the essential elements for safe operation of a nuclear licensed site is the availability to the licensee in sufficient numbers
of suitably qualified and experienced people to carry out and manage the operations and associated design work. In the last
few years, there have been a number of reports to illustrate the recent and current problems of recruiting such people to work in the
traditional locations for nuclear personnel in the North-West of England. Concern for the immediate future is exacerbated by a peculiar
demographic of the people currently employed in positions demanding higher level skills.
In response to the growing realization that there is an impending skills gap that needs to be filled, Sellafield Talent Management
team (and latterly with support of the NDA) have been working with a number of education and training providers to put in
place bespoke courses aimed at overcoming this shortage. In the absence of a steady stream of willing graduates from technical and
management courses, the primary strategy has been to encourage life-long learning and up-skilling amongst its employees, targeting
those who, for whatever reason upon leaving school, missed their opportunity to study and progress to train at a high level, but
who possess that potential and have now developed a keenness to proceed with that study in later life.
One Foundation Degree has been selected for development of a unique approach to higher education. <strong>The</strong> work of University
of Central Lancashire and its West-Cumbrian education and training partners has featured as a case study in other media, but this
paper reports on a fresh development within that work: co-delivery.
SESSION 10 - EM LIFE-CYCLE ECONOMICS AND COST-BENEFIT ANALYSIS
1) UK NUCLEAR DECOMMISSIONING AUTHORITY - VALUE FRAMEWORK,
ITS DEVELOPMENT AND ROLE IN DECISION MAKING - 16399
Mark Wareing, NDA (UK)
As part of its day to day business NDA must be able to demonstrate that it is delivering value for money across its entire estate,
as this is essential to securing funding from government and demonstrating to stakeholders that NDA is delivering on its mission.
Value comes in many forms such as an improved environment, hazard reduction, changes in sky line, social amenities, money,
employment etc. Depending on the perspective of the receiver, and their closeness to the effected area, the relative weighting they
place on the different aspects of value will vary. <strong>The</strong>refore the challenge to NDA has been how to get a consistent approach to measuring
value that is broadly acceptable to stakeholders and allows the different aspects of value to be compared and decisions made
on a national basis. This paper describes the work undertaken by NDA to
2) STRATEGIC ENVIRONMENTAL ASSESSMENT FOR UK LLW MANAGEMENT - 16392
Andrew Craze, Matthew Clark, NDA (UK); Pete Davis, EntecUL Ltd. (UK)
NDA is delivering a Strategic Environmental Assessment (SEA) to sit alongside the UK Nuclear Industry Low Level Waste
Strategy. <strong>The</strong> purpose of this assessment is to fulfil our requirements under the European Unions Strategic Environmental Assessment
(SEA) Directive (2004/42/EU) and transposing UK Regulations, and to underpin the development of the strategy. <strong>The</strong> outputs
of the SEA have provided input into particular aspects of the strategy, leading to a more robust and informed result.
Development of options to be assessed under the SEA has looked at a number of factors, including:
• what the strategy is aiming to achieve
• expectation from stakeholders as to what should be addressed
• consideration of tactical approaches to implementation of the strategy in addition to high level strategic issues
• links to other projects and programmes (for example the Environmental Safety Case for the Low Level Waste Repository
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Abstracts Session 10-12
<strong>The</strong> SEA aims to provide a robust assessment of the environmental impacts of alternative strategies for providing continued
capability and capacity for the management and disposal of LLW in the UK. <strong>The</strong> assessment also considers other, more tactical,
issues around implementation of the strategy, for example: issues around the location of LLW management facilities; the environmental
impacts of alternative waste treatment options (metal recycling etc); considerations of alternative approaches to the classification
of radioactive waste and opportunities that would result.
Critical to the development of the SEA has been the involvement of statutory and non-statutory stakeholders, who have
informed both the output and the approach taken.
3) THE INVENTORY OF NUCLEAR LIABILITIES — A MISSION OF PUBLIC INTEREST - 16317
Christian Cosemans, Jacques Cantarella, Gerda Bal, ONDRAF/NIRAS (Belgium)
<strong>The</strong> safe management of a countrys radioactive substances in both the short and the long term implies a cost to its present society
and necessitates financial resources to cover these costs. Once they are needed, these financial resources may prove to be insufficient
or even completely lacking, leading to a nuclear liability. By virtue of article 9 of the Belgian law of <strong>12th</strong> December 1997,
the Belgian Government wishes to avoid the occurrence of such nuclear liabilities. This law charges ONDRAF/NIRAS, the Belgian
Agency for Radioactive Waste and Enriched Fissile Materials with the mission to draw up a register of the localisation and the
state of all nuclear sites and all sites containing radioactive substances, to estimate the costs of their decommissioning and remediation,
to evaluate the existence and adequacy of the provisions for financing these future or current operations and to update the
resulting inventory of nuclear liabilities on a five-yearly basis.
This paper outlines the methodology put in place by ONDRAF/NIRAS to accomplish this assignment and highlights some of
the results of this exercise. It than focuses on the main recommendations ONDRAF/NIRAS made to the Belgian Government on
the field of avoiding potential nuclear liabilities.
4) FINANCIAL RISKS OF POST-CLOSURE CUSTODIAL CARE FOR THE BARNWELL
RADIOACTIVE WASTE DISPOSAL FACILITY - 16155
Robert Baird, Washington Division, URS Corporation (USA);William Newberry, South Carolina Energy Office (USA)
This paper reports evaluations of the adequacy of the Barnwell Extended Care Fund in light of identified risks, with the conclusion
that the fund is sufficient to cover the costs and uncertainties associated with planned post-closure care of the Barnwell,
South Carolina low-level radioactive waste disposal facility. It reviews background information pertinent to the facilitys post-closure
monitoring and maintenance and describes financial responsibility for post-closure activities. It identifies and briefly characterizes
the activities planned to be conducted following facility closure and presents the mid-range estimate of planned post-closure
costs. <strong>The</strong> paper identifies and quantifies sources of uncertainty in activities and costs planned for post-closure care and presents
50-, 80-, and 95-percent confidence levels of planned costs. <strong>The</strong> fund is currently sufficient to cover some but not all of the costs
that might be incurred as a result of unplanned events. <strong>The</strong> paper identifies, characterizes, and quantifies unplanned events, possible
consequences, and probabilities of occurrence. <strong>The</strong> paper presents costs that might be incurred in responding to the unplanned
initiating events and identifies levels of confidence that the fund is adequate to cover such costs.
SESSION 11A - PANEL: YGN ROUNDTABLE “AN AUDIENCE WITH”...
ABSTRACTS NOT REQUIRED
SESSION 12 - POSTER SESSION: SPENT FUEL, FISSILE, TRU AND HLW MANAGEMENT
A) SELECTIVE UPTAKE OF PALLADIUM FROM HIGH-LEVEL LIQUID WASTES BY HYBRID
MICROCAPSULES ENCLOSED WITH INSOLUBLE FERROCYANIDES - 16382
Hitoshi Mimura, Takashi Sakakibara, Wu Yan, Yuichi Niibori,Toyko University (Japan);
Shin-ichi Koyama, Takashi Ohnishi, Japan Atomic Energy Agency (Japan)
<strong>The</strong> fine crystalline powders of KCuFC were immobilized with alginate gel polymers by sol-gel methods. <strong>The</strong> uptake properties
of KCuFC-microcapsules (KCuFC-MC) were examined by batch and column methods. <strong>The</strong> size of KCuFC-MC particle was
estimated to be about 1 mm in diameter, and KCuFC powders were uniformly dispersed in KCuFC-MC particles. <strong>The</strong> uptake rate
of Pd2+ for KCuFC-MC was attained within 3 d, and the uptake of Pd2+ was independent of the temperature and coexisting HNO3 concentration. As for the breakthrough properties of Pd2+ through the column packed with KCuFC-MC, breakpoint of 5% breakthrough
was enhanced with lowering of flow rate and independent of coexisting HNO3 concentration. <strong>The</strong> Pd2+ ions were selectively
adsorbed on KCuFC crystal phase, while other metal ions such as Ru(NO) 3+ and ZrO2+ ions on alginate phase. High uptake
percentage of 98.6 % was obtained by using the dissolved solutions of spent fuel from FBR-JOYO (119 GWd/t, JAEA). <strong>The</strong> alginate
film enclosing KZnFC was further prepared by using the support of cellulose filter paper, and Pd2+ ions were selectively
adsorbed on the KZnFC-MC film. <strong>The</strong> alginate film enclosing insoluble ferrocyanides is expected for the selective separation of
Pd2+ as an ion-exchange filter. Thus, the microcapsules enclosing insoluble ferrocyanides are effective for the selective separation
of Pd2+ from high-level liquid wastes (HLLWs).
B) UPTAKE OF 14C-ACETIC ACID BY RICE PLANT AS RELATED TO ROOT FUNCTION
AND MICROBIAL ACTIVITY ON THE ROOT SURFACE - 16111
Shinichi Ogiyama, National Institute of Radiological Sciences(Japan); Nobuyoshi Ishii,
Shigeo Uchida, National Institute of Radiological Sciences (Japan)
Experiments using rice plants (Oryza sativa L.) were conducted to examine uptake of 14C-acetic acid via the root and 14C behavior on the root surface. For hydroponics, three types of rice plants were cultured with 14C-acetic acid solution: complete plant,
half-rooted plant, and non-rooted plant. Also, for the root incubation experiment, sterilized root and non-sterilized root were incubated
with 14C-acetic acid solution. <strong>The</strong> 14C radioactivities in the plant parts and solution were measured. Non- and half-rooted
plant had 14C radioactivity in their aerial part, but the complete plant did not. <strong>The</strong> trends of radioactivity levels in the solution were
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Session 12 Abstracts
directly opposite to those of plant root biomass. A high level 14Cof 14C radioactivity was observed on the entire root surface of nonsterilized
root in the incubation experiment, and 14C radioactivity in the solution also remarkably decreased from 7 h to 96 h after
the 14C addition. <strong>The</strong>se results suggest that the amount of 14C-acetic acid absorbed by the plant through the roots is very small.
However, the plant absorbs 14C-acetic acid through breaks in the roots. Once 14C-acetic acid is inside the plant, it immediately
transfers to the shoots. Degradation of 14C radioactivity in the solution and 14C fixation on the root surface arise from the context
of microbial activities.
C) CHARACTERISTICS ON THE SAP-BASED WASTEFORM CONTAINING
RADIOACTIVE MOLTEN SALT WASTE - 16137
Hwan-Seo Park, In-Tae Kim, Hwan-Young Kim,
Byeung-Gil Ahn, Han-Soo Lee, Korea Atomic Energy Research Institute (Korea)
This study investigated a unique wasteform containing molten salt wastes which are generated from the pyro-process for the
spent fuel treatment. Using a conventional sol-gel process, SiO2-Al2O3-P2O5 (SAP) inorganic material reactive to metal chlorides
were prepared. By using this inorganic composite, a monolithic wasteform were sucessfully fabricated via a simple process, reaction
at 650℃ and sintering at 1100℃. This unique wasteform should be qualified if it meets the requirements for final disposal.
For this reasons, this paper characterized its chemical durability, physical properties, morphology and etc. In the SAP, there are
three kinds of chains, Si-O-Si as a main chain, Si-O-Al as a side chain and Al-O-P/P-O-P as a reactive chain. Alkali metal chlorides
were converted into metal aluminosilicate(LixAlxSi1-xO2-x ) and metal phosphate(Li3PO4 and Cs2AlP3O10 ) while alkali earth
and rare earth chlorides were changed into only metal phosphates (Sr5(PO4)3Cl and CePO4). <strong>The</strong>se reaction products were compatible
to borosilicate glasses which were functioned as a chemical binder for metal aluminosilicate and a physical binder for metal
phosphates. By these phenomena, the wasteform was formed homogenously above μm scale. This would affect the leaching behaviors
of each radionuclides or component of binder. <strong>The</strong> leach rates of Cs and Sr under the PCT-A test condition were about 10- 3g/m2day. <strong>The</strong> physical properties (Cp, k, ρ, Hv, and etc) were very reasonable. Other leaching tests (ISO, MCC-1P) are on-going.
From these results, it could be concluded that SAP can be considered as an effective stabilizer on metal chlorides and the method
using SAP will give a chance to minimize the waste volume for the final disposal of salt wastes through further researches.
D) REALISTIC INTEGRATION OF SORPTION PROCESSES IN TRANSPORT
PROGRAMS FOR LONG-TERM SAFETY ANALYSIS - 16370
Madlen Stockmann, FZ Dresden-Rossendorf (Germany);Vinzenz Brendler, Forschungszentrum Dresden-Rossendorf e.
(Germany) Ulrich Noseck, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH (Germany)
Safety assessment of radioactive waste repositories in salt rock formations considers the overlying sedimentary rock above the
salt domes as important barrier. Sorption on mineral surfaces of the sediment can retard the transport of many contaminants, namely
radionuclides, considerably. Previously, the retention of radionuclides has been described in respective computer programs by
temporally constant distribution coefficients.
In the present study, an existing transport program r3t is extended towards a more realistic description of the radionuclide
migration under changing geochemical conditions. <strong>The</strong> methodology developed here is based on a description of the sorption of
radionuclides as a function of important influence factors such as pH, pCO2, ionic strength, and the mineral phases being present.
Applying surface complexation models, multidimensional matrices of smart Kd-values can be computed a-priori. <strong>The</strong> reactive
transport model r3t then can call for each time-space point Kd values adapted for the correct geochemical conditions. <strong>The</strong> biggest
challenge here was finding a fast and robust algorithm for search and averaging in multidimensional matrices with non-equidistant
population. First results are presented for a test case where respective site-specific geochemical conditions in the overlying rock
have been evaluated, mainly consisting of tertiary and quaternary sands and clays.
E) EMERGING CHALLENGES IN NUCLEAR WASTE MANAGEMENT IN INDIA
IN VIEW OF ITS EXPANSION PROGRAMME - 16364
Murty.S Ganti, Andhra University (India)
Presently the contribution of nuclear power to the total power production in India is around 4000 MWe and about 2500 MWe
will be added by the year 2010. Plans are are ahead to add another 15000 MWe by the end of XI th plan with import options.
Estimates show that in India about 2000 t of natural uranium was irradiated in PHWRs 533t in research reactors and 397t in
BWR by the end of the year 2000. How ever the BWR fuel which is slightly enriched and spplied remained unprocessed ( as spent
fuel) while the rest is under reprocessing. Thisese operations generated about 5000 cubic meters of HLW 35000 cubic meters of
ILW.
India’s reprocessing was initiated in 1964 with PUREX technology with Al clad natural uranium from Canada India research
reactorat Trombay. Based on this experiance reprocessing facilities for power reactor fuels was developed sucesfully.Further fast
Breeder test reactor mixed carbide fuel reprocessing plant was installed at kalpakkam with a view to process fuels from FBR with
mixed oxide and metallic fuels in future.<strong>The</strong> challenges to be addressed in tackling these future fuels with high burn up levels will
be highlighted.
F) TOWARDS AN IMPLEMENTING GEOLOGICAL DISPOSAL TECHNOLOGY PLATFORM IN EUROPE - 16365
Marjatta Palmu, Posiva Oy, (Finland); Torsten Eng, SKB (Sweden)
Several European waste management organizations have started the work on creating a technology platform to accelerate the
implementation of deep geological disposal of radioactive waste in Europe. <strong>The</strong>re is an increasing consensus in the international
community about geological disposal as the preferred option for solving the long-term management of spent fuel, high-level waste,
and other long-lived radioactive wastes. At the same time, the European citizens have a widespread wish for a solution for highlevel
radioactive waste disposal. A majority of the European countries with nuclear power have active waste management programmes,
but the current status and the main challenges of those programmes vary. <strong>The</strong> most advanced waste management programmes
in Europe (i.e. Sweden, Finland and France) are prepared to start the licensing process of deep geological disposal facilities
within the next decade. Despite the differences between the timing and the challenges of the different programmes, there is a
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Abstracts Session 12
joint awareness that cooperation on the scientific, technical, and social challenges related to geological disposal is needed, and the
cooperation will be beneficial for the timely and safe implementation of the first geological disposal facilities. Such a demonstration
of a viable solution for the management of high-level radioactive waste will enhance stakeholder confidence in Europe. Several
decades of research, development and demonstration (RD&D) have been carried out in the field of geological disposal. <strong>International</strong>
opportunities of cooperation and establishing a technology platform were explored in the European Commission co-funded
projects like Net.Excel and CARD. According to the CARD project, the majority of the funding for RD&D in waste management
comes from the implementing organizations.
G) WVP MELTER ANALYSIS AND MODELLING FOR LIFETIME EXTENSION - 16209
Clare Booth, Sellafield Sites (UK); Mark D’Vaz, Sellafield Ltd (UK)
<strong>The</strong> purpose of the Sellafield Waste Vitrification Plant (WVP) is to immobilise highly active liquors produced during reprocessing
of magnox and oxide fuel operations by means of a Vitrification process bonding the fission products as metal oxides into
a borosilicate glass matrix. This provides the stability required for safe long term storage of waste fuel products.
Over the last two years the WVP technical department has carried out a study in prolonging the life of the melter vessels used
within WVP. <strong>The</strong> melter vessel is a critical part of the vitrification process. <strong>The</strong> purpose of this vessel is a crucible in which to heat,
mix and react glass and fission products (as a calcine) and pour the glass product into a stainless steel container for long term storage.
Several research projects have been carried out in partnership with the National Nuclear Laboratory to further understand the
failure mechanisms within the melter vessel. Research has been focused in two areas:
• <strong>The</strong> metallographic destructive examination of two inactive melters used to simulate plant conditions experienced within
WVP active lines with respect to thermal recycling and corrosion attack. From relating this work to plant process data such
as thermal cycling temperatures and HAL chemical composition, a set of operation parameters can be established with the
intention of prolonging the life of the melter vessels within WVP.
• <strong>The</strong> development of modelling techniques. <strong>The</strong> models have been designed to simulate a variety of operating conditions
and aim to predict behaviour of the vessel and melt in a large variety of control regimes, and glass characteristics for a
large set of feed compositions. From this information we can formulate operating envelopes that extend the life of the
melter vessel by anticipating required operating conditions given different feedstocks and mitigating or postponing primary
failure modes.
H) FEBEX IN SITU TEST - SHOWING THE VALUE OF VERY LONG TERM (>10 YEARS) EXPERIMENTS - 16422
Irina Gaus, NAGRA (Switzerland); Erik Thurner, SKB (Sweden); Marjut Vahanen, Posiva, (Finland);
Pedro Luis Martín Martín, CIEMAT (Spain); Juan Carlos Mayor, ENRESA (Spain);
Jose Luis García-Siñeriz, Aitemin, (Spain); Antonio Gens, UPC (Spain)
<strong>The</strong> FEBEX experiment at the Grimsel Test Site (GTS) consists of an in-situ full-scale engineered barrier system (EBS) test
for the disposal of high level waste (HLW) performed under natural conditions.
With heating starting in 1997 and led by Enresa, the FEBEX experiment, is the longest running experiment of its scale and has
been the research subject in three subsequent European projects. In 2008, a consortium of four partners (SKB, Ciemat, Posiva,
Nagra) continued running the experiment under the project name FEBEXe until at least 2012, when excavation of the second and
last heater is planned.
<strong>The</strong> experiment is based on the Spanish reference concept in crystalline rock in which the canisters are placed horizontally in
drifts and surrounded by a clay barrier constructed of highly compacted bentonite blocks. A constant temperature of 100°C has been
maintained, while the bentonite buffer has been slowly hydrating in a natural way. A total of 632 sensors were installed in the clay
barrier, the rock mass, the heaters and the service zone to measure the following variables: temperature, humidity, total pressure,
displacement, water pressure etc. Partial dismantling and sampling of the in-situ test was carried out during 2002.
Although one of the main goals of the experiment has been fulfilled (demonstrating the feasibility of handling and constructing
the EBS), with the length of the dataset increasing, the observed thermo-hydro-mechanical (THM) and thermo-hydro-geochemical
(THG) behaviour has revealed several features of interest, such as the underestimation of re-saturation times and the degree of
uncertainty in key parameters.
I) PARTITIONING RATIOS AMONG SOLID-, LIQUID-, AND GAS-PHASES FOR C-14
LABELED SODIUM ACETATE IN PADDY AND UPLAND SOILS - 16112
Nobuyoshi Ishii, National Institute of Radiological Sciences (Japan)
In Japan, transuranic (TRU) waste is grouped into four types. Group 2 type includes hulls and end pieces, which contain significant
amounts of C-14. As C-14 is long-lived, soluble and has little sorption properties, it is the key nuclide in safety assessment
for a geological repository of TRU waste.
Recently, the possibility of leaching of organic carbon compounds from hull waste has been reported. However, there is little
information for reliable migration data sets of such organic C-14. Thus, it is hard to deny any possible migration of organic C-14
from a TRU repository site to the sphere of human habitation.
To assess human expose to C-14 through crops intake, it is necessary to understand the behavior of organic C-14 in agricultural
fields. In this study, we determined solid-, liquid-, and gas-partitioning ratios of organic C-14 in paddy and upland soils by using
batch cultures. Investigation of factors affecting the partitioning ratios between paddy soils and upland soils was also carried out.
Paddy soils (n = 63) and upland soils (n = 79) were collected from throughout Japan. Each of these agricultural soils was flooded
with deionized water at a solid-liquid ratio of 1:10 in a bottle. <strong>The</strong> flooded samples supplemented with [1, 2-14C] sodium acetate
were shake-incubated for 7 days. At the end of incubation, radioactivites of C-14 in the soil suspension and the supernatant were
counted by using liquid scintillation counting. Values of the sample pH were measured at the end of incubation.
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Session 12-14 Abstracts
J) A STUDY ON THE ONCE-THROUGH BACK-END FUEL CYCLE SCENARIO - 16129
Yoon Hee Lee, Kunjai Lee,Kunjai Lee, KAIST (Korea);Jongsoon Song, Chosun University (Korea)
<strong>The</strong>re are three options for spent fuel management, recycle, once-through and wait and see. <strong>The</strong> national policy for spent fuel
in Korea is wait and seeand it has to be clearly decided for spent fuel management. <strong>The</strong> final disposal is the last stage is essential
even though the recycling option will be chosen for spent fuel management. And the long-term management considering safety and
retrievability is needed.
In this study, once-through fuel cycle was focused on for back-end fuel cycle. <strong>The</strong> international trend for SF management policy
and the Korean situation has been investigated. <strong>The</strong> once-through back-end fuel cycle scenarios has been developed and
screened. It is evaluated that the technical and economical aspect for the scenarios.
<strong>The</strong> optimal scenario has been derived by relative comparison and the long-term SF management strategy has been proposed
which satisfies both domestic conditions and international trends.
K) AERODYNAMIC RESISTANCE OF A NEW FILTERS FOR CS-137
VAPOUR CAPTURE AT HIGH TEMPERATURE - 16146
Albert Aloy, Alexander Strelnikov, Khlopin Radium Institute (Russia);
Sergey Rovny, Nikolay Pyatin, PA “Mayak” (Russia)
Major characteristics of two alumosilicate filters based on fly ash (FAF) and porous shamotte (PS) were studied for high-temperature
trapping of Cs-137 vapours. To determine aerodynamic resistance of the filters, a test facility was designed and built to
determine that the aerodynamic resistance of the initial PS was significantly lower than that of the FAF at linear air flows up to 15
cm/sec.
<strong>The</strong>rmal treatment at 1400-15000С made it possible to increase mechanical strength of the PS by factors of 1.5- 3.4, without
any significant aggravation of other characteristics that exceeded similar parameters for the FAF.
L) SEPARATION OF RARE EARTH PRECIPITATES FROM LICL-KCL EUTECTIC SALTS
BY A DISTILLATION AT A REDUCED PRESSURE -16162
Hee-Chul Eun, Korea Atomic Energy Research Institute(Korea); Hee-Chul Yang,
Yung-Zun Cho, Han-Soo Lee, In-Tae Kim, Korea Atomic Energy Research Institute (Korea)
Distillation and condensation characteristics of LiCl-KCl eutectic salts containing rare earth precipitates were investigated to
separate the rare earth precipitates from the salts effectively. <strong>The</strong> distillation flux of the salts was increased by about 1,000 times
by reducing the ambient pressure from 760 Torr to 0.5 Torr. <strong>The</strong> salt vapors were almost changed into salt lumps during a salt distillation
at the ambient pressure of 0.5 Torr and they were collected in the condensed salt storage. However, fine salt particles were
formed when the salt distillation was processed at 10 Torr and it is difficult for them to be recovered. <strong>The</strong>refore, it is thought that
a salt vacuum distillation and condensation should be processed to recover almost all of the vaporized salts at a pressure below 0.5
Torr.
M) DEVELOPMENT OF A LCC STRUCTURE FOR THE RECOVERY OF
ACTINIDES FROM MOLTEN SALT - 16167
Seungwoo Paek, Si-Hyung Kim, Dal-Seong Yoon, Joon-Bo Shim, Do-Hee Ahn,
Han-Soo Lee, Korea Atomic Energy Research Institute (Korea)
Pyroprocessing technologies have been known as the non-proliferation process in the treatment of spent nuclear fuel, because
actinide elements, including uranium and TRU, and small amounts of rare earth fission products could be simultaneously recovered
using LCC (Liquid Cadmium Cathode). However, the electro-deposition of a U/TRU mixture on a LCC has been recognized
to be disturbed by the growth of uranium dendrites which act as a solid cathode resulting in the obstruction of TRU deposition.
<strong>The</strong>refore, the inhibition of the growth of uranium dendrite on LCC is considered as a key technique for the electrowinning process.
In this study, the stirrer type and the mesh type LCC structures have been prepared to develop a LCC assembly with a high efficiency.
<strong>The</strong> electro-deposition behaviors of uranium on the different type LCC structures in molten salt electrolyte were investigated
to make an efficient LCC assembly. <strong>The</strong> experimental results showed that the mesh type LCC could crash the uranium dendrite
at LCC interface and precipitate it into the bottom of a cadmium crucible. Several experiments were conducted under various operating
conditions such as the current density and the salt concentration to optimize the design of LCC.
N) THE STANDARD-LEGAL REGULATION OF SNF IMPORT FROM FOREIGN
REACTORS IN THE RUSSIAN FEDERATION - 16171
Nekhozhin Mikhail (Russia)
Abstract not available.
70
SESSION 13 - PANEL: EMERGING ISSUES IN THE MANAGEMENT FOR L/ILW
ABSTRACTS NOT REQUIRED
SESSION 14 - PANEL: INTERNATIONAL DECOMMISSIONING NETWORK
ABSTRACTS NOT REQUIRED

Abstracts Session 15
SESSION 15 - DISPOSAL SITE AND WASTE FORM CHARACTERIZATION AND PERFORMANCE ASSESSMENT
1) A PRELIMINARY POSTCLOSURE SAFETY ASSESSMENT OF OPGS PROPOSED
L&ILW DEEP GEOLOGIC REPOSITORY, CANADA - 16289
Richard Little, Quintessa Limited (UK); John Avis, Nicola Calder, Intera Engineering Limited (Canada); Nava Garisto,
Senes Consultants Limited (Canada) Paul Gierszewski, Helen Leung, Nuclear Waste Management Organization
(Canada);Laura Limer, James Penfold, George Towler, Russell Walke,Robert Walsh, Quintessa Limited (UK)
Ontario Power Generation (OPG) is proposing to build a Deep Geologic Repository (DGR) for Low and Intermediate Level
Waste (L&ILW) near the existing Western Waste Management Facility at the Bruce site in the Municipality of Kincardine, Ontario.
<strong>The</strong> Nuclear Waste Management Organization (NWMO), on behalf of OPG, is currently preparing an Environmental Impact Statement
(EIS) and Preliminary Safety Report (PSR) for the proposed repository. This involves investigation of the site’s geological
and surface environmental characteristics, conceptual design of the DGR, and technical studies to demonstrate the operational and
long-term safety of the proposed facility. A preliminary postclosure safety assessment (SA) was undertaken in 2008 and 2009.
Consistent with the guidelines for the preparation of the EIS for the DGR and the regulatory guide on assessing the long-term
safety of radioactive waste management, the SA evaluated the DGR’s performance and its potential impact on human health and
the environment through pathway analysis of contaminant releases, contaminant transport, receptor exposure and potential effects.
Consideration was given to the expected long-term evolution of the repository and site following closure (the Normal Evolution
Scenario) and four disruptive (what if) scenarios (Human Intrusion, Severe Shaft Seal Failure, Open Borehole, and Extreme Earthquake),
which considered events with uncertain or low probability that could disrupt the repository system.
2) NUMERICAL ASSESSMENT OF THE LONG-TERM SAFETY OF THE MORSLEBEN REPOSITORY
FOR LOW- AND INTERMEDIATE-LEVEL RADIOACTIVE WASTE - 16346
Juergen Wollrath, Juergen Preuss, Bundesamt fuerStrahlenschutz (BfS) (Germany); Dirk-Alexander Becker, Joerg
Moenig, Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH (UK)
<strong>The</strong> Morsleben repository has been in operation since 1971 as a repository for low- and intermediate-level radioactive waste.
Until the end of the disposal phase in 1998 a waste volume of about 37,000 m3 with a total activity of 4.5·1014 Bq was disposed
of. Currently, the German Federal Office for Radiation Protection (BfS) is applying for the licence to finally close the repository.
Concerning the possible release of radionuclides to the biosphere, the repository is subject to German radiation protection regulations.
<strong>The</strong>ir fulfilment has to be proven by means of numerical calculations as a part of the safety case.
A simplified repository model has been developed by GRS and used for calculating the consequences of different scenarios
and variants, as well as for a probabilistic uncertainty and sensitivity analysis. <strong>The</strong> application for licensing is, among others, based
on these results.
In this paper the main features of the model and the underlying assumptions, as well as the most important calculation results
are presented and explained.
3) THE DEVELOPMENT AND USE OF T2GGM: A GAS MODELLING CODE FOR THE POSTCLOSURE SAFETY
ASSESSMENT OF OPGS PROPOSED L&ILW DEEP GEOLOGIC REPOSITORY, CANADA - 16291
Paul Suckling, Quintessa Limited (UK); Nicola Calder, Intera Engineering Limited (Canada);
Paul Humphreys, University of Huddersfield (UK); Fraser King, Integrity Corrosion Consulting Limited Canada);
Helen Leung, Nuclear Waste Management Organization (Canada)
As part of the postclosure safety assessment of Ontario Power Generation’s (OPG’s) proposed Deep Geologic Repository
(DGR) for Low and Intermediate Level Waste (L&ILW) at the Bruce site, Ontario, a Gas Generation Model (GGM) has been developed
and used to model the detailed generation of gas within the DGR due to corrosion and microbial degradation of the organics
and metals present.
<strong>The</strong> GGM is based on a kinetic description of the various microbial and corrosion processes that lead to the generation and
consumption of various gases. It takes into account the mass-balance equations for each of the species included in the model,
including three forms of organic waste (cellulose, ion-exchange resins, and plastics and rubbers), four metallic waste forms and
container materials (carbon and galvanised steel, passivated carbon steel, stainless steel and nickel-based alloys, and zirconium
alloys), six gases (CO2 , N2, O2 , H2 , H2S, and CH4 ), five terminal electron acceptors (O2 , NO3 , Fe(III), SO 2-
4 , and CO2 ), five forms
of biomass (aerobes, denitrifiers, iron reducers, sulphate reducers, and methanogens), four types of corrosion product (FeOOH,
FeCO3 , Fe3O4 , and FeS), and water. <strong>The</strong> code includes the possibility of the limitation of both microbial and corrosion reactions
by the availability of water.
4) CURING TIME EFFECT ON THE FRACTION OF 137CS FROM IMMOBILIZED
RADIOACTIVE EVAPORATOR SLUDGE BY CEMENT - 16329
Ilija Plecas, Slavko Dimovic, Vinca Institute (Serbia)
Traditional methods of processing evaporator concentrates from NPP are evaporation and cementation.<strong>The</strong>se methods allow to
transform a liquid radioactive waste into the rather inert form, suitable for a final disposal. To assess the safety for disposal of
radioactive mortar-waste composition, the leaching of 137Cs from immobilized radioactive evaporator concentrate into a surrounding
fluid has been studied. Leaching tests were carried out in accordance with a method recommended by IAEA. Curing conditions
and curing time prior to commencing the leaching test are critically important in leach studies since the extent of hydration of the
cement materials determines how much hydration product develops and whether it is available to block the pore network, thereby
reducing leaching. Incremental leaching rates Rn (cm/d) of 137Cs from evaporator concentrates after 180 days were measured. <strong>The</strong>
results presented in this paper are examples of results obtained in a 20-year concrete testing project which will influence the design
of the engineer trenches system for future central Serbian radioactive waste storing center.
71

Session 15-16 Abstracts
5) MODELLING LONG-TERM CORROSION OF CEMENTED WASTE FORMS IN SALT BRINES - 16202
Bernhard Kienzler, Volker Metz, Forschungszentrum Karlsruhe (Germany)
Since 1979, leaching and corrosion experiments have been performed at the Asse II salt mine using simulated full-scale
cemented waste forms. <strong>The</strong> cement blocks, doped with 137Cs and uranium, have been exposed to saturated salt brines. <strong>The</strong> brines
have been sampled regularly and analysed with respect to the mobilized radionuclides, pH, and major solution components. In
2006, four of the cement blocks samples were recovered and solid samples were obtained by drilling vertically into the corroded
cement forms. <strong>The</strong> drill cores as well as abraded drill dust were analysed with respect to chemical and mineralogical compositions,
distributions of radionuclides and major waste components, thermogravimetric and mechanical properties. Results of these methods
show consistently that cement forms, having an initial W/C = 0.5, were homogeneously corroded in MgCl2 rich brine. No vertical
or radial variations were found with respect to major chemical components and mineral phases. In the cement blocks corroded
in NaCl saturated brine, spatial heterogeneities in the distribution of major anions (chloride, nitrate) and the trace cation Cs+
show that these cement / NaCl systems have not been completely homogenized within 22 years. Concentration profiles of Cl-, NO3 - and Cs+ were compared with calculated profiles to quantify diffusion coefficients and to get information on the kinetics of relevant
processes. Simulations of chemical alteration of the cement / brine system indicate that both MgCl2-rich and NaCl systems are
close to equilibrium with respect to stabilities of secondary mineral phases.
6) COUPLING TIME-DEPENDENT SORPTION VALUES OF DEGRADING
CONCRETE WITH A RADIONUCLIDE MIGRATION MODEL - 16220
Janez Perko, Dirk Mallants, Diederik Jacques, Lian Wang,Belgian Nuclear Research Centre SCK-CEN (Belgium)
Safety assessment of radioactive waste disposal facilities is usually carried out by means of simplified models. Abstraction of
the numerical model from the real physical environment is done in several steps. One of the most challenging issues in safety
assessment concerns the long time scales involved and the evolution of engineered barriers over thousands of years. For some
processes occurring in specific engineered barriers the uncertainties related to long time scales are addressed by implementing conservative
assumptions in the radionuclide migration models. Other processes such as chemical concrete degradation, however, can
be estimated for long time periods by the use of coupled geochemical transport models. For many near-surface disposal facilities,
concrete is a very important engineered barrier because it is used in the construction of disposal modules or vaults, in production
of high-integrity monoliths and their backfilling and for waste conditioning. Knowledge on the durability of such concrete components
and its relation to radionuclide sorption is important for a defensible safety assessment. Chemical degradation typically occurs
as the result of decalcification, dissolution and leaching of cement components and carbonation. <strong>The</strong>se reactions induce a gradual
change in the solid phase composition and the concrete pore-water composition, from “fresh” concrete porewater with a pH above
13 to a pH lower than 10 for “evolved” porewater associated with fully degraded concrete.
7) A NUMERICAL STUDY OF FACTORS AFFECTING RADIOACTIVE
GAS MIGRATION IN THE FAR-FIELD - 16273
Elina Kuitunen, Michael A. Hicks, <strong>The</strong> University of Manchester (UK)
Gases are produced in radiological waste repositories through several processes. While the bulk of the gas produced is expected
to be hydrogen, some gases labelled with radionuclides such as tritium and carbon-14 are also formed. <strong>The</strong> consequences of the
generation and migration of these gases need to be assessed in order to ensure the safety of a radiological waste repository.
Different disposal concepts are employed internationally to deal with repository gases and radionuclide migration. This paper
presents the results of preliminary analyses carried out using the code TOUGH2. Specifically, parametric studies for simplified
geometries have been carried out in order to assess the relative importance of the governing parameters of gas migration. This forms
the first stage of numerically assessing the safety of different repository designs with regards to radioactive gas migration. By identifying
the near-field factors with the highest impacts on gas migration in the far-field, the repository designs can be further
improved.
SESSION 16 - NATIONAL AND INTERNATIONAL PROGRAMS FOR SPENT FUEL, FISSILE,
TRU, AND HLW MANAGEMENT
1) NUMO-RMS: A PRACTICAL REQUIREMENTS MANAGEMENT SYSTEM FOR THE LONG-TERM
MANAGEMENT OF THE DEEP GEOLOGICAL DISPOSAL PROJECT - 16304
Hiroyoshi Ueda, Satoru Suzuki, Katsuhiko Ishiguro, NuclearWaste Management Organization of Japan (NUMO)
(Japan);Kiyoshi Oyamada, JGC Corporation (Japan); Shoko Yashio, Obayashi Corporation (Japan);
Matt White, Roger Wilmot,Galson Sciences Limited (UK)
NUMO (Nuclear Waste Management Organization of Japan) has the responsibility for implementing deep geological disposal
of high-level (HLW) and transuranic (TRU) radioactive waste from the Japanese nuclear programme. A formal Requirements Management
System (RMS) is planned to efficiently and effectively support the computerized implementation of the management strategy
and the methodology required to drive the step-wise siting processes, and the following repository operational phase,. <strong>The</strong> RMS
will help in the comprehensive management of the decision-making processes in the geological disposal project, in change management
as the disposal system is optimised, in driving projects such as the R&D programme efficiently, and in maintaining structured
records regarding past decisions, all of which lead to soundness of the project in terms of long-term continuity.
<strong>The</strong> system is planned to have information handling and management functions using a database that includes the
decisions/requirements in the programme under consideration, the way in which these are structured in terms of the decisionmaking
process and other associated information. A two-year development programme is underway to develop and enhance an existing trial
RMS to a practical system. Functions for change management, history management and association with the external timeline management
system are being implemented in the system development work. <strong>The</strong> database format is being improved to accommodate
the requirements management data relating to the facility design and to safety assessment of the deep geological repository.
72

Abstracts Session 16
2) STRATEGIC PLAN FOR THE MANAGEMENT OF SPENT NUCLEAR PLAN - 16024
Hitesh Nigam, Edgardo (Gary) DeLeon, Department of Energy, Washington, DC,United States
<strong>The</strong> Nuclear Waste Policy Act of 1982 established geologic disposal as the United States policy for disposal of spent nuclear
fuel (SNF) and high-level radioactive waste (HLW). <strong>The</strong> Department of Energy (DOE) has established programs and plans to disposition
its SNF and HLW at the geologic repository in accordance with this Act. <strong>The</strong> DOE Office of Civilian Radioactive Waste
Management is responsible for the disposition of all DOE managed SNF, commercial SNF, and HLW. Yucca Mountain in Nevada
has been selected as the geologic repository site and is planned to commence operation in 2020. <strong>The</strong> DOE Office of Environmental
Management (EM) is responsible for safe, secure, and cost-effective storage of its SNF and HLW, preparing its SNF and HLW
for shipment, and meeting the acceptance criteria of the geologic repository. <strong>The</strong> focus of this presentation is to discuss DOE EM
Strategic Plan for the management of approximately 2,400 metric tons SNF.
EM has to work very diligently with its many stakeholders and protect the environment and the health and safety of workers
and the public to manage its inventory of SNF, which is located primarily at 4 sites around the country. However, EM is also responsible
for managing SNF from many research reactors in the U.S. as well as foreign research reactors. Majority of the EMs SNF is
dry stored, the remaining SNF is in wet storage, with plans to dry store in the future.
3) DISPOSAL TECHNOLOGIES FOR SPENT FUEL FROM GERMAN NUCLEAR POWER PLANTS - 16028
Reinhold Graf, GNS mbH, Essen,Germany, Wolfgang Filbert, DBE Technology GmbH, Peine,Germany, Klaus-Jürgen
Brammer, GNS mbH, 45127 Essen,Germany, Wilhelm Bollingerfehr, DBE Technology GmbH, 31224 Peine,Germany
<strong>The</strong> direct disposal of spent fuel as a part of the current German reference concept was developed as an alternative to spent
fuel reprocessing and vitrified HLW disposal. <strong>The</strong> technical facilities necessary for the implementation of this part of the reference
concept the so called POLLUX-concept, e.g. interim storage buildings for casks containing spent fuel, a pilot conditioning facility,
and a special cask POLLUX for final disposal - have been built. With view to a geological salt formation all handling procedures
for the direct disposal of spent fuel for the repository were tested aboveground in a test facility at a 1:1 scale. To optimise the
reference concept all operational steps have been reviewed for possible improvement. <strong>The</strong> two most promising variants resulting
from this optimisation process for direct disposal of SF are the BSK 3 -concept and the DIREGT-concept. <strong>The</strong> latter one is the most
recent developed concept and has been designed for the direct disposal of large multipurpose casks. Both concepts rely on borehole
emplacement technology, vertical boreholes for the BSK3-concept und horizontal boreholes for the DIREGT-concept. <strong>The</strong>
paper describes these two favoured concept variants and their status as of today with focus on the BSK3-concept.
Supported by the EU and the German Federal Ministry of Economics and Technology DBE TECHNOLOGY GmbH built an
aboveground test facility at a 1:1 scale to simulate all relevant handling procedures for the BSK 3-concept and GNS as representative
of the German utilities provided the procurement of the hard-ware components. Up to now about 200 emplacement cycles have
been performed successfully. <strong>The</strong> emplacement system in total comprises the emplacement device, the borehole lock, a transport
cart, a transfer cask, which will shuttle between the aboveground conditioning facility and the underground repository, and the
BSK3-canister itself, designed to contain fuel rods from three PWR-fuel assemblies with a total of about 1.5 t HM. <strong>The</strong> BSK3-concept
simplifies the operation of the repository by using the same handling procedures and techniques that will be developed for the
disposal of reprocessing residues.
4) CHARACTERISTICS OF THE SPENT FUEL GENERATED IN KOREA - 16227
Dong Hak Kook, Korea Atomic Energy Research Institute, Daejeon,Korea (Republic), Jongwon CHOI, Korea Atomic
Energy Research Institute, Daejon,Korea (Republic), Heuijoo Choi, DongKeun Cho, Korea Atomic Energy Research
Institute, Daejeon,Korea (Republic)
Nuclear power has satisfied the national electric power demand for three decades, and there are only two reactor types in Korea.
<strong>The</strong> nuclear fuel species, however, have a large variety of fuel types, dimensions, initial enrichment, and fuel supply vendors. A
spent fuel accumulation problem has arisen like any other country that uses nuclear power. <strong>The</strong> spent fuel wet storage capacity in
the reactor pool is getting close to its limit, and so hence, short & long-term solutions are being actively proposed.
First the general status for the nuclear industries and spent fuels will be introduced, then spent fuel characteristics will follow,
and last the future anticipation of spent fuel management will close this article.
keywords: spent fuel, characteristic, Korea
5) NEW SAFETY CONCEPT FOR GEOLOGICAL DISPOSAL IN JAPAN 9 -16339
Kazumi Kitayama, Nuclear Waste Management Organization of Japan, Tokyo,Japan
This paper describes a new safety concept for the Japanese geological disposal program, which is a development of the conventional
multi-barrier system concept. <strong>The</strong> Japanese government established the Nuclear Waste Management Organization of
Japan (NUMO) as an implementation body in 2000 based on the Final disposal actfollowing the publication of the H-12 Report,
which confirmed the scientific and engineering feasibility of HLW geological disposal in Japan. Since then, NUMO has undertaken
further technical developments aimed at achieving safe and efficient implementation of final disposal. <strong>The</strong> safety concept developed
in the H-12 Reportprovides sufficient safety on the basis of site-generic considerations. However, it is considered to be overconservative
and therefore does not represent the most probable performance of the engineered or natural barriers. Recently, concrete
measures have been proposed requiring the safety case to be presented in terms of a realistic assessment of the most probable
performance. This approach takes into account the safety functions of both engineered and natural barriers as well as the longterm
static geochemical equilibrium. In particular, the evolution of the safety performance of engineered and natural barriers can
be efficiently augmented by the realistic long-term geochemical equilibrium.
73

Session 16-17 Abstracts
6) PROPOSALS ON MANAGEMENT OF AMB SNF - 16169
Nekhozhin Mikhail, FSUE FCNRS, Moscow,Russia
A.V. Yescherkin, V.A. Zotov, S,V. Kazakov, M.A. Nekhozhin, V.P. Smirnov, FSUE FCNRS (Russia);
D.A. Goncharov, OOO NPF Sosny, Dmitrovgrad; E.G. Kudryavtsev, A.V. Khapyorskaya,
Rosatom; Kovacz Y., Hamvas, I., NPS Paks, (Hungary)
AMB SFAs have been storing more than 50 years in cassettes in cooling ponds BV-1 and BV-2 of BNPS Phase 1. Cassettes
are defined as chromium or carbon steel tubes in bundles containing 17 and 35 pieces. At the present time, the condition of these
ponds cannot guarantee safe operation in all modes of SNF storage and management. Accident risk depends, on the one hand, on
expired service life of pond cladding, on the other hand, by unsatisfactory state of SFA and carbon steel cassettes in which spent
fuel assemblies are stored.
<strong>The</strong> previously adopted technology of management of AMB SFA envisaged construction of a dry storage facility in Zheleznogorsk
on the basis of the existing RBMK storage facility, delivery of cassettes with AMB SFA there and a long-term storage. This
technology has a number of significant drawbacks such as:
• complicated development of a safe method of cassette transportation relative to justification of nuclear and radiation safety
as well as limits on hydrogen build-up;
• taking into account that AMB SFAs are 14 m long, dimensions of the facility would increase drastically;
• the problem of nuclear and radiation safety as well as accumulation of hydrogen in storage is not easier than that in transportation;
• technology does not provide a final solution of AMB SFA management;
• AMB fuel contains chemically active ingredients; so it is desirable to make them safer, for example, by fuel processing.
7) AN OVERVIEW ON THE NATIONAL RADWASTES MANAGEMENT STRATEGY
INTO THE CONTEXT OF THE NUCLEAR PROGRAM DEVELOPMENT - 16356
Maria RADU, CENTER OF TECHNOLOGY AND ENGINEERING FOR NUCLEAR OBJECTIVES (CITON),
MAGURELE, ILFOV,Romania, Adrian PANAIT, CENTER OF TECHNOLOGY AND ENGINEERING FOR NUCLEAR
OBJECTIVES (CITON), Magurele,,Romania, Gheorghe Negut, National Agency for Radioactive Waste (ANDRAD)
ROMANIA, MIVENI, ARGES,Romania, Cristian Litescu, National Agency for Nuclear Waste (ANDRAD) Romania,
MIOVENI, ARGES,Romania
At present the main radwaste generator is Cernavoda NPP with 2 x 700 MW units in operation. For the year 2016, the Plant is
predicted to have 4 units in operation.
<strong>The</strong> National Strategy for radioactive waste management was drafted by National Agency for Radioactive Waste (ANDRAD),
the jurisdictional authority for coordinating spent nuclear fuel and radioactive waste management in Romania.
Last year, the Government of Romania established that a new nuclear power plant would be build, so, with this future operational
NPP, the quantity of waste will increase from the today evaluations.
<strong>The</strong>refore the national strategy for radioactive waste management should be reviewed accordingly.
<strong>The</strong> paper presents some preliminary results obtained upon the R&D Programs related to the radioactive waste disposal facilities.
SESSION 17 - HLW CHARACTERIZATION / RECENT ADVANCES IN HLW TREATMENT SYSTEMS
1) SEPARATION OF FISSION PRODUCTS AND ACTINIDES FROM SAVANNAH
RIVER SITE HIGH-LEVEL NUCLEAR WASTES - 16174
David T. Hobbs, Thomas B. Peters, Michael R. Poirier, Fernando F. Fondeur, Charles A. Nash, Samuel D. Fink,
Savannah River National Laboratory, Aiken, SC,United States
Separation methods for the pretreatment of the liquid fraction of high-level nuclear waste (HLW) at the Savannah River Site
(SRS) include solvent extraction for the separation of cesium and adsorption/ion exchange for the removal of strontium and alphaemitting
actinides. <strong>The</strong> solvent extraction process, referred to as Caustic Side Solvent Extraction or CSSX, uses a calixarene extractant
in combination with phase modifiers in a hydrocarbon diluent. Monosodium titanate (MST), a hydrous metal oxide, is the baseline
material for the removal of strontium and alpha-emitting radionuclides (principally 238Pu, 239Pu, 240Pu and 237Np). Two
pretreatment facilities, the Modular Caustic Side Solvent Extraction Unit (MCU) and the Actinide Removal Process (ARP) facility
began radioactive operations at SRS in 2008. Together these facilities can treat approximately 4 million liters of waste per year.
<strong>The</strong> same separation processes are also planned for the much larger Salt Waste Processing Facility (SWPF). <strong>The</strong> SWPF, which has
a design throughput of about 27 million liters per year, is scheduled to begin radioactive operations in 2013.
This paper presents an overview of the separation processes as well as recent research and development activities aimed at
improving separation performance in the pretreatment facilities.
2) SAFETY ASSESSMENT OF GEOLOGICAL DISPOSAL OF HIGH-LEVEL RADIOACTIVE
WASTE IN BOOM CLAY: RELATION WITH THE RADIONUCLIDE INVENTORY - 16418
Pierre Van Iseghem, SCK.CEN, Mol,Belgium
This paper discusses the impact of the parameter values used for the transport of radionuclides from the radioactive waste to
the far-field on the Safety Assessment study for the proposed geological disposal in a Boom Clay formation in Belgium. <strong>The</strong>
methodology of the Safety Assessment is explained, and the results of the Safety Assessment for vitrified high-level waste and spent
fuel are presented. <strong>The</strong> radionuclides having the strongest impact on the dose-to-man for both HLW glass and spent fuel are 79Se,
129I, 126Sn, 36Cl, and 99Tc. Some of them are volatile, and for many of them there is no accurate information on their inventory
in the waste form. We therefore recommend to spend attention to obtain a more accurate inventory of these critical radionuclides
in the HLW forms. <strong>The</strong> hypotheses in the selection of the main parameter values are further discussed, together with the status of
the R&D on one of the major critical radionuclides (79Se).
74

Abstracts Session 17
3) DESIGN OF PYROPROCESS DIGITAL MOCKUP AND WORKSPACE ANALYSIS OF DEVICES - 16140
Hee Seoung Park, Chang-Hwan Choi, Sung-Hyun Kim, Byung-Seok Park, Ki-Ho Kim,
Ho-Dong Kim, Korea Atomic Energy Research Institute (Korea)
Pyroprocessing is an alternative technology that entails certain advantages in regard to reduce the quantity of the disposable
spent fuel and to realize a more efficient and effective spent fuel management. <strong>The</strong> Korea Atomic Energy Research
Institute(KAERI) has been carried out various types of experiments in order to demonstrate pyroprocessing which can achieve a
more efficient and effective spent fuel management at the Advanced spent fuel Conditioning Process Facility(ACPF). Pyroprocessing
which can deal with a spent fuel requires a high manipulator skillfulness of a human operator. A remote manipulation environment
that a human operator has to observe is the inner side of a hotcell through a lead grass window which has many obstacles due
to many existing ‘blind-spots’ where are several cameras installed. <strong>The</strong> lack of visual information when operating in a cluttered
environment makes manoeuvering a manipulator very difficult and when this situation is exacerbated by strict time limits for a task
completion, then a manipulator and environmental collisions and resultant damage can occur. This article introduces a system that
can model nuclear facilities and devices with a low cost and can simulate a deployment analysis, a remote accessibility, and a
remote interchangeability effectively and proposes a scheme to enable an operator to improve a remote manipulation by using a
haptic device. For implementing a system which is composed of various modules, we have been built a new Graphic User Interface(GUI)
which enables a user to access the system easily and to obtain results concisely. In order for a virtual manipulator to
access the devices in a virtual environment, we describe the mathematical background in relation to the forward and inverse kinematics.
To establish if a virtual manipulator can be processed normally with a remote accessibility and operability, a case study for
interface between a human operator and the haptic device was carried out. This paper describes an experiment for the deployment
analysis of the MSM, which has five revolute joints and one prismatic joint with joint limitations by referring to a manipulator
workspace boundary generation algorithm.
4) DESIGNING A NEW HIGHLY ACTIVE LIQUOR EVAPORATOR - 16075
Paul Robson, Emma Candy, Sellafield Limited, Seascale, Cumbria,United Kingdom
<strong>The</strong> Highly Active Liquid Effluent Storage (HALES) plant stores, concentrates and conditions Highly Active Liquor (HAL) in
evaporators for buffer storage in Highly Active Storage Tanks (HAST). Highly Active (HA) evaporators play a pivotal role in the
delivery of reprocessing, historic clean up and hazard reduction missions across the Sellafield site. In addition to the engineering
projects implemented to extend the life expectation of the current evaporator fleet, the UK Nuclear Decommissioning Agency
(NDA) is sponsoring the construction of a new HA evaporator (Evaporator D) on the Sellafield site.
<strong>The</strong> design and operation of the new HA evaporator is based on existing/recent HA evaporator technology but learning from
past operational experience. Operational experience has been a key area where the existing plant operators have influenced both
the new design itself and the requirements for commissioning and training. Many of the learning experiences require relatively simple
engineering design modifications such as a new internal washing provision and transfer line blockage recovery systems, they
are never-the-less expected to significantly improve the flexibility and operational capability of the new evaporator.
Issues that the project delivery team has addressed as part of the development of the design and construction have included:
• Minimising interruptions and/or changes to the normal operations of interfacing plants during construction, commissioning
and operation of the new facility.
• Modularisation of the plant, enabling fabrication of the majority of the plant equipment off-site within a workshop (as
opposed to on-site) environment improving Quality Assurance and reducing on-Site testing needs
• Drawing out the balance between operational and corrosion resistance improvements with actual design and delivery needs
• Provision of a new facility reliant on the infrastructure of an existing and ageing facility and the competing demands of
the related safety cases
5) THE HYDROLYSIS OF HYDROXAMIC ACID COMPLEXANTS
IN THE PRESENCE OF NON-OXIDIZING METAL IONS - 16230
Fabrice Andrieux, University of Central Lancashire (UK); Colin Boxall, Lancaster University (UK);
Iain May, Los Alamos National laboratory (UK); Robin J Taylor, National Nuclear Laboratory (UK)
Hydroxamic acids are salt free, organic compounds with affinities for cations such as Fe3+ , Np4+ and Pu4+ , and have been identified
as suitable reagents for the control of Pu and Np in advanced nuclear fuel reprocessing. Acid catalyzed hydrolysis of free
XHAs is well known and may impact negatively on reprocessing applications. <strong>The</strong> hydrolysis of metal-bound XHAs within metal
ion-XHA complexes is less understood.
With the aid of speciation diagrams, we have modelled UV-visible spectrophotometric kinetic studies of the acid-catalyzed
hydrolysis of acetohydroxamic acid (AHA) bound to the model ion Fe(III). <strong>The</strong>se studies have yielded the following information
for the hydrolysis of AHA in the Fe(AHA)2+ complex at 293 K: (i) the order with respect to [H+] during the rate determining step,
m=0.97, is the same as for the free ligand, indicating a similarity of mechanisms; and (ii) the kinetic rate parameter, k1=1.02×10?4
dm3?mol?1?s?1, is greater than that for the free ligand, a result that is consistent with a Hammett analysis of the system.
<strong>The</strong> results of a UV-visible, near-IR spectrophotometric study of the 1:1 and 2:1 complexes formed between formo- and acetohydroxamic
acids (FHA, AHA) and Np(IV) ions are interpreted using speciation diagrams and the previously obtained kinetic
model. Consequently, the complexation constant for formation of the 1:1 Np(IV)-FHA complex in nitric acid is estimated at and
indications are that complexation protects the ligand against hydrolysis.
75

Session 17-18 Abstracts
6) DEVELOPING CERAMIC BASED TECHNOLOGY FOR THE
IMMOBILISATION OF WASTE ON THE SELLAFIELD SITE - 16049
Martin Stewart, Sam Moricca, Tina Eddowes, Yingjie Zhang,Eric Vance, Gregory Lumpkin,
Melody Carter, ANSTO(Australia); Mike James, Mark Dowson, Sellafield (UK)
National Nuclear Laboratory, in collaboration with the Australian Nuclear Science and Technology Organisation, is developing
hot isostatic press (HIP) based ceramic technology for the immobilisation of a diverse range of wastes arising from nuclear fuel
processing activities on the Sellafield site. Wasteform compositions have been identified and validated for the immobilisation of
these plutonium containing wastes and residues in glass-ceramic and ceramic forms. A full scale inactive facility has been constructed
at NNLs Workington Laboratory to support the demonstration of the technology. Validation of the inactive wasteform development
using plutonium has been carried out at ANSTOs Lucas Heights facility. A feasibility study has been conducted to evaluate
the construction and operation of a plutonium active pilot facility which would demonstrate the immobilisation of actual residues
in the NNL Central Lab. This could form the basis of a facility to treat the plutonium wastes and residues in their entirety. <strong>The</strong> technology
is being explored for the immobilisation of additional wastes arising on the Sellafield site taking advantage of the investment
already made in skills and facilities.
7) THE USE OF HOT-ISOSTATIC PRESSING TO PROCESS NUCLEAR WASTE FORMS - 16253
Martin Stewart, Sam Moricca, Tina Eddowes, Yingjie Zhang,Eric Vance, Gregory Lumpkin,
Melody Carter, ANSTO (Australia); Mike James, Mark Dowson, Sellafield (UK)
ANSTO has developed a combination of tailored nuclear wasteform chemistries coupled with the use of flexible hot-isostatic
pressing processing technology to enable the successful incorporation of problematic nuclear wastes into dense, durable monoliths.
This combined package also enables the design of wasteforms with waste loadings well in excess of those achievable via baseline
melting routes using borosilicate glass as hot-isostatic pressing is not constrained by factors such as glass viscosity, crystallisation
and electrical conductivity. In this paper we will discuss some of our experiences with problematic wastes e.g.: plutonium wastes,
sludges and HLW such as the Idaho calcines.
8) DESIGN INNOVATIONS FOR THE MANAGEMENT OF ALPHA
CONTAMINATED UNSERVICEABLE GLOVE BOXES - 16224
R.K. Gupta, D.S Sandhanshive, S.R. Shendge, A.K. Singh, M.N.B. Pillai,
Arun Kumar, PP Mazumdar, Bhabha Atomic Research Centr (India)
With the maturing of nuclear industry, there is an added burden on the Back End of fuel cycle. Radioactive facilities and radiological
laboratories, commissioned decades ago, are in the need for refurbishment or shutting down. This has kept the waste managers,
the world over, busier than ever in finding out solutions towards safe handling and disposal of different types and categories
of radioactive wastes as an essentiality for environmental remediation. In the Indian context, several Pu-contaminated Glove Boxes
were occupying premium storage space in radiological laboratories pending a safe and viable solution for their final management.
This paper describes the steps adopted for managing such unserviceable Glove Boxes.
<strong>The</strong> first step consisted of in-situ encasement of individual Glove Boxes, encountering the challenges of low head room and
space congestion in these laboratories with cognizance to regulatory requirement related to radiation safety. <strong>The</strong> second step was
removal, transfer and placement of encased Glove Boxes in a dedicated facility under continuous surveillance. <strong>The</strong> glove boxes
will remain stored in this facility until arrangements are completed for dismantling and volume reduction in another facility which
is under design. <strong>The</strong> final step is the development of an appropriate technique for dismantling/cutting of Glove Boxes in an alphatight
facility constructed to prevent airborne activity, collection of cut pieces and storage in manageable containers. First two steps
in the overall management of glove boxes have already been successfully completed and the third, comprising of the development
and design of a dedicated cutting facility is underway. While the design and in-situ handling of Glove Boxes and the engineering
efforts of the first two steps have been adequately detailed in this treatise, the contents of the paper are largely devoted to describing
the possible options for cutting/dismantling/remote-handling of the Glove Boxes. <strong>The</strong> description also includes hands on evaluation
of tools and gadgets in a full-scale pilot set-up with a view to incorporating the most credible choice in an upcoming active
facility.
SESSION 18 - D&D OF POWER REACTORS AND RESEARCH REACTORS
1) TRANSPORT OF THE REACTOR PRESSURE VESSELS IN THE
GREIFSWALD NUCLEAR POWER PLANT - 16012
Ralf Borchardt, Energiewerke Nord GmbH (Germany)
Five WWER-440 reactors are being dismantled on the Greifswald Nuclear Power Plant (KGR) site.<strong>The</strong> strategy for the dismantling
of the reactor units 1 to 4 (operation time 12 - 17 years) was to cut and pack the components remotely. For this purpose
dry and wet cutting areas were installed. <strong>The</strong> remote cutting and packing of the reactor pressure vessel and its internals was successfully
tested with non-activated original reactor components of units 7 and 8 from October 1999 until July 2003. From August
2004 until July 2007 the internals from reactor units 1 and 2 were cut, packed and transported to the on-site Interim Store North
(ISN).
For the reactor 5 it was planned to transport the RPV in one piece and the reactor internals in shielding and transport containers
to the interim store for decay storage.
In December 2003 the RPV of unit 5 was lifted and transported to the interim store. From April 2006 up to July 2006 the reactor
internals of unit 5 were packed and transported to the interim store.
76

Abstracts Session 18
After the evaluation of the experience made during the transport and the radiological measurements and samplings taken from
the RPV unit 1, the strategy for the dismantling of the reactors was changed. <strong>The</strong> reactor pressure vessels of the units 1 to 4 and
the reactor internals of the units 3 and 4 should be removed as complete parts and stored as shielded large components in the ISN.
In summer 2005 EWN applied for the new strategy at the responsible licensing authority and in August 2007 this license was granted.
In November 2007 the reactor pressure vessels of the units 1 and 2 were transported into the ISN. <strong>The</strong> transport of the reactor
pressure vessels and the internals from units 3 and 4 is planned in the period from March till September 2009.
<strong>The</strong>se transports of the reactor pressure vessels and internals show that the dismantling of the reactors with dismantling and
interim storage of large components could not only be an alternative for cutting but could also be favored from the economical and
radiological point of view.
2) TECHNOLOGY DEVELOPMENT FOR DECOMMISSIONING IN FUGEN AND CURRENT STATUS - 16108
Koichi Kitamura, Japan Atomic Energy Agency (Japan);Kazuya Sano, Yasuyuki Nakamura,
Akira Matsushima, Masahiro Ishiyama, Hidehiko Matsuo, Masashi Tezuka, Takahiro
Haneda,Japan Atomic Energy Agency (Japan)Reginald Coomans, Tecnubel (Belgium)
<strong>The</strong> decommissioning program of proto-type Advanced <strong>The</strong>rmal Reactor (ATR) FUGEN has started in 2008 as first decommissioning
of the commercial-scale water reactor. It consists of four periods, considering the transportation of spent fuels and the
radioactive decrease of highly activated materials. It is expected that the whole program of decommissioning will be completed
until 2028.
Now, the decommissioning is under the first period, spent fuels and heavy water has been carrying out from FUGEN, and a
part of the turbine system with relatively low radioactive contamination has been dismantled.
FUGEN has a complicated core structure consisting 224 fuel channels with pressure tubes and calandria tank, etc. and used
heavy water as moderator, unlike other light water reactor (LWR). <strong>The</strong> materials of the core structure were highly activated due to
a long term operation, tritium and C-14 were generated, and the facilities were contaminated by them. Thus, it is important to study
the dismantling technology of the reactor core and the decontamination technology, considering characteristics of FUGEN such as
core structure and radioactive inventory in advance.
In this presentation, the contents of the decommissioning program and its current status such as dismantling work of a part of
the turbine system, the studying situation of dismantling technology of reactor core using Abrasive Water Jet (AWJ) which is a candidate
of cutting technologies, the examination of tritium decontamination in heavy water system, the study of decontamination
technology for C-14 will be presented mainly.
3) SEEKING THE OPTIMUM SOLUTION FOR REACTOR DECOMMISSIONING WASTE – 16391
Lisa Hughes, NDA (UK)
<strong>The</strong> current baseline plan for reactor decommissioning waste in the UK is to package the waste in to approved containers pending
geological disposal. <strong>The</strong> waste arising from reactor decommissioning currently accounts for 35% by volume of the total waste
destined for geological disposal in the UK. <strong>The</strong> majority of this waste (approximately 30% by volume of the UK total) is graphite
from reactor cores.
<strong>The</strong> NDA Strategy published in March 2006 and the current NDA business plan both made a commitment to explore management
and treatment options for reactor graphite waste. Since this commitment NDA has carried out a work programme on graphite
options. CoRWM’s recommendation on reactor decommissioning wastes in 2006 and Governments response also recognised the
need for alternative solutions for all wastes arising from reactor decommissioning.
Since the publication of these reports NDA has initiated the Reactor Decommissioning Wastes project. This project will examine
the hazard reduction and potential cost benefit of options of alternative management of reactor decommissioning waste. This
will focus on Magnox reactors in the NDA estate, but in considering the position with regard to the large waste graphite liability,
will also take account of the eventual decommissioning of graphite moderated AGR reactors owned by British Energy.
This paper will provide an overview of the project, the proposed approach, options under consideration and timescales for
development.
4) MODELLING OF RADIATION FIELDS AND ESTIMATION OF DOSES DURING
DISMANTLING OF RBMK-1500 REACTOR EMERGENCY CORE COOLING SYSTEM - 16247
Povilas Poskas, Audrius Simonis, Lithuanian Energy Institute(Lithuania)
<strong>The</strong>re is only one nuclear power plant in Lithuania Ignalina NPP. <strong>The</strong> INPP operated two similar units with installed capacity
of 1500 MW (each). RBMK-1500 were commissioned in 12/1983 and 08/1987, and the original design lifetime was projected out
to 2010 and 2015 respectively. But the first Unit of Ignalina NPP was shutdown December 31, 2004, and second Unit will be closed
down in 2009.
In relation with this, implementation of new technologies for treatment and conditioning of radioactive waste, construction of
the interim dry storage facility for spent nuclear fuel and preparation of the licensing documents for decommissioning of the Unit
1, and some other projects were implemented or are under implementation at Ignalina NPP. Implementation of dismantling activities
requires detailed knowledge of the radiological situation at the Unit 1. General Radiological Characterization Program for
Ignalina NPP Unit 1 based on NUREG-1575 was prepared in 2005-2006 and approved by Regulatory Bodies.
In 2008 development of the dismantling projects at Ignalina NPP Unit 1 has been started. Dismantling project of the emergency
core cooling system (Building 117/1) is the first project in this field. Based on the radiological surveys data, detailed modeling of
the radiation fields has been performed using VISIPLAN 3D ALARA Planning tool computer program (SCK CEN, Belgium). So,
in this paper detailed information on radiation fields modelling, proposals for optimization of the radiation doses to the personnel,
and emergency core cooling system equipment dismantling is presented.
77

Session 18 Abstracts
5) DISMANTLING THE REACTOR CONTAINMENT OF GERMANY´S FIRST NPP - 16272
Ludger Eickelpasch, NUKEM Technologies GmbH (Germany)
Decommissioning and dismantling of a Nuclear Power Plant (NPP) is a challenging task with very long duration. Coming to
the very end of a dismantling project it is still worth to think about optimization possibilities such as parallel work. Some additional
constrains generated by parallel activities may raise but it can still be effective due to reduction of the overall project schedule
5) USE OF REMOTE EQUIPMENT IN REACTOR DECOMMISSIONING - 16326
Scott Martin, Matt Cole, Scott Adams, S.A.Robotics (USA)
Nuclear reactor decommissioning continues to remain at the forefront of the energy and defence industries as many reactors
built from the 1940s to the 1970s are reaching the end of their life cycles. As demand for decommissioning increases, the focus on
workers health and safety has become paramount. This focus on worker safety, coupled with the unique challenges faced in reactor
decommissioning, continues to promote the use of remote equipment in the decommissioning process. New technologies available
in the market today have also created new opportunities for the implementation and application of remote equipment for reactor
decommissioning. <strong>The</strong>se technologies include: carbon fibre, high pressure liquid cutting, and advanced control packages. Also,
the methods for remote deployment of existing decommissioning technologies such as flame cutting, shearing, and heavy equipment
continue to evolve.
This paper will focus on the use of this technology at the following facilities: the decommissioning of the Rancho Seco reactor
in California, the Brookhaven graphite research reactor in New York, the Windscale Pile 1 Reactor in the United Kingdom, and
the Fort St. Vrain HTG Reactor in Colorado. <strong>The</strong>se have all used remote equipment and emerging technologies to solve complex
problems in nuclear reactor decommissioning.
<strong>The</strong> purpose is this paper is to outline some of the challenges associated with reactor decommissioning, describe new technologies
and deployment techniques being used in the decommissioning field, and to provide an overview of projects using these new
technologies.
7) EXPERIENCE IN CHEMICAL DECONTAMINATION OF PWR SYSTEMS AND COMPONENTS - 16274
Claude Steinkuhler, DDR Consult (Belgium); KoenLenie, Reginald Coomans, Tecnubel (Belgium)
Tecnubel has recently performed various chemical decontamination of French and Belgian Pressurized Water Reactors (PWR)
systems and components. <strong>The</strong> purpose of this paper is to present and compare these experiences. <strong>The</strong> objectives of these operation
were the reduction of the general surface contamination together with the elimination of hot spots in Residual Heat Removal Systems
(RHRS), Chemical and Volume Control Systems (CVCS) and Reactor Coolant Pumps (RCP). This reduction of contamination
leads to the reduction of dosimetry to the maintenance personnel and allows the works on critical equipment. An additional
challenge for three of these projects lay in the execution of a complicated operation on the critical path of a reactor refueling shutdown.
<strong>The</strong> chemical decontamination were performed by circulating an adequate fluid in the systems or around the components.
Since the contamination was generated at hot conditions during power operation, a redox attack on the surface was necessary. <strong>The</strong>
EDF systems and components were decontaminated using a qualified EDF process of the EMMAC family. <strong>The</strong> Reactor Coolant
Pump from the Belgian PWR was treated with the NITROX process, qualified by Westinghouse. <strong>The</strong> functions required by the
decontamination system were very diverse and therefore an existing decontamination loop, which was previous developed for the
decontamination of small circuits, was re-developed and adapted for bigger volumes by DDR Consult and Tecnubel. <strong>The</strong> results of
five decontamination are presented and detailed in terms of efficiency and waste production. <strong>The</strong>se projects were: the chemical
decontamination of the RHRS of Flamanville 1 NPP, of the CVCS non regenerative heat exchanger at St Laurent des Eaux NPP,
of the RHRS and CVCS of Bugey 2 NPP and of two RCP at the Westinghouse Belgian Service Center.
8) ASSESSMENT OF DECOMMISSIONING WASTE FOR KOREAN STANDARD NUCLEAR POWER PLANT - 16126
Jai-Hoon Jung, Han-Jung Na, Jung-Su Park, Byung-Sik Lee,Jong-Hyuck Lee, KOPEC (Korea)
Decommissioning Waste for Korean Standard Nuclear Power Plant (KSNP) was assessed. <strong>The</strong> reference plant is Yonggwang
Unit 1 (YGN1), Westinghouse 950 MWe Pressurized Water Reactor (PWR). YGN1 is located in Yonggwang site, east-south coast
of Korean peninsula, where totally 6 units are in operation. YGN1 started commercial operation in 1986 and is expected to be
decommissioned in the year 2026 after the lifetime of 40 years. YGN1 shares some buildings such as radwaste building with YGN2.
<strong>The</strong>refore, the decommissioning waste from common buildings was redued to half of assessed waste for one unit. According to
Korean regulation, waste is classified into 2 groups; one is high level waste (HLW) and the other is intermediate and low level waste
(ILLW). By engineering judgment, waste disposal criteria are classified into 4 groups; i.e., HLW, ILLW (GTDC: greater than disposal
criteria), ILLW and EW (exempted waste). Waste type is classified by 11 groups; i.e., spent fuel, metal-small, metal-large,
concreted-scabbled, concrete-debris, soil, resin-primary loop decontamination, resin & filter, dry active waste, Asbestos containing
material, and hazard material. In order to reduce waste volume, all wastes should be processed by melting, abrasive blasting, chemical
decontamination, steam reforming, soil assay, incineration, supercompaction, etc.
* This paper will review and present detailed results of assessed waste for KSNP
78

Abstracts Session 19
SESSION 19 - GLOBAL PARTNERING IN INTERNATIONAL CLEAN-UP PROGRAMS
1) DECOMMISSIONING AND DISMANTLING SOLUTION DEVELOPMENT FOR VOLODARSKY CIVIL
NUCLEAR FLEET SUPPORT SHIP - 16386
Konstantin N. Koulikov, Rinat A. Nisamutdinov, NIPTB ONEGA OAO (Russia);
Andrey N. Abramov, Atomflot FGUP (Russia), Anatoly I. Tsubanikov, Aspect-Conversion ANO(Russia)
Having about 200 tons of solid radioactive waste aboard, the Volodarskiy Floating Technical Base (FTB) is a potential radiation
pollution source for the Murmansk region and Kola Bay, as her long-term berthing negatively affects the hull structures. <strong>The</strong>reby,
FSUE Atomflot collaborated with ANO Aspect-Konversia and JSC NIPTB Onega within the frameworks of Federal Specialpurpose
Program Assurance of Nuclear and Radiation Safety for 2008 and for the period up to 2015 and developed the Volodarskiy
FTB dismantling concept.
In 2008 in the course of development of the Volodarskiy FTB dismantling concept the following works were carried out:
1) vessel condition survey, including SRW radiological analysis;
2) feasibility study of the Volodarskiy FTB dismantling alternatives (options). In this regard the following options were analyzed:
• formation of the package assembly in the form of vessels undivided hull for durable storage in the Saida long-term
storage facility (LTSF);
• formation of individual SRW package assemblies for durable storage in the Saida LTSF;
• comprehensive recycling of all solid radioactive waste by disposal in protective containers.
3) selection and approval of the dismantling option. <strong>The</strong> option of formation of individual SRW package assemblies for
durable storage in the Saida LTSF was selected by the Rosatom State Corporation. In this case the works will be performed
on a step-by-step basis at the Atomflot enterprise and SRE Nerpa. <strong>The</strong> conceptual dismantling technology was developed
for the selected Volodarskiy FTB dismantling option.
<strong>The</strong> proceedings contain description of alternatives, analysis procedure and proposal for further study of mentioned challenge.
2) DISMANTLEMENT OF NUCLEAR POWERED SUBMARINES IN RUSSIA - 16414
Alexey Maltsev, JSC SC Zvyozdochka (Russia)
<strong>The</strong> report represents an experience and an overview of the present-day situation at the Shiprepairing Center JSC SC ZVYOZ-
DOCHKA. <strong>The</strong> report describes the dismantling process of nuclear powered submarines (NPS) at the shipyard as well as the complex
for dismantlement. <strong>The</strong>res also an overview of opportunities, problems and perspectives of their solving as regards the leading
shipyard in the sphere of NPS dismantlement.
3) ENVIRONMENTAL ASSESSMENTS OF NUCLEAR SUBMARINE
DECOMMISSIONING IN THE RUSSIAN FAR EAST - 16360
Michael Washer, Department of Foreign Affairs and <strong>International</strong> Trade (Canada); Mark Gerchikov, AMEC NSS
(Canada); Michael Cull, Teledyne Brown Engineering (USA) Konstantin Koulikov, NIPTB Onega (Russia)
Pursuant to the Canadian Environmental Assessment Act (CEAA) and the Projects Outside Canada (POC) Regulations, the
NPS project in the Russian Far East was subject to Environmental Assessment.
Environmental impacts were assessed for the following activities:
• Transportation of two NPS from a naval base in Petropavlovsk-Kamchatsky to the Zvezda shipyard in Bolshoi Kamen
using Heavy Lift Vessel.
• Implementation of all activity required for de-fuelling and dismantling six NPS including reactor de-fuelling, radioactive
and hazardous waste management, and spent nuclear fuel management.
• Related infrastructure activities such as upgrading the local Bolshoi Kamen railway to ensure safe transportation of spent
nuclear fuel out of the region.
Detailed assessments encompassed analysis of impacts of radioactivity, impacts on atmosphere, surface water resources, aquatic
and terrestrial environment, geology and hydrogeology and analysis of socio-economic, health and cultural considerations. As
part of the process, a consultation strategy was developed and implemented which included public consultation meetings in Bolshoi
Kamen where the Zvezda shipyard is located.
<strong>The</strong> paper will describe the assessment, public consultation and recommended mitigation measures for the Canadian NPS dismantlement
program in the Russian Far East.e optimization leading to the lowest radiation exposure of personnel handling the filled
fibre-reinforced containers is discussed.
4) REMEDIATION OF GREMIKHA COASTAL MAINTENANCE BASE IN NORTH-WEST RUSSIA - 16279
Boris S. Stepennov, Kurtchatov Institution (Russia); Alexandre Gorbatchev,
CEA (France); Lucien Pillette-Cousin, AREVA TA (France)
<strong>The</strong> former coastal base in Gremikha is located in the Kola Peninsula, along the Barents Sea, 270 km from Murmansk. It was
constructed in 1961-1966 for providing operation of Russian nuclear submarines, particularly for receipt and temporary storageof
spent nuclear fuel (SNF) unloaded from reactors and for storage of solid and liquid radioactive waste (SRW and LRW). Remediation
of the coastal base in Gremikha (TSF) is one of the main priorities of Rosatom in order to evacuate all spent fuel, the eight
spent cores from Alfa-class submarines, SRW and LRW, and eventually to perform site remediation. In the framework of the Global
Partnership Against the Spread of Weapons and Materials of Mass Destruction, launched at the G8 Kananaskis summit in June
2002, France has funded a comprehensive survey of the site, pre-design studies, some detailed studies for SNF evacuation and work
on infrastructures to prepare safe evacuation of nuclear materials. On behalf of Rosatom, the Kurtchatov Institute ensures a role of
coordination of the Gremikha Remediation Project. France is represented by the Atomic Energy Commission (CEA), with the technical
assistance of AREVA TA.
79

Session 20-21 Abstracts
SESSION 20 - PANEL: GLOBAL PARTNERING IN INTERNATIONAL WASTE AND CLEANUP PROGRAMS
ABSTRACTS NOT REQUIRED
SESSION 21 - ENVIRONMENTAL MANAGEMENT HEALTH AND SAFETY ISSUES
1) DOSE ASSESMENT OF PERSONNEL HANDLING CONDITIONED RADIOACTIVE WASTE - 16149
Michal Panik, Matej Zachar, Vladimir Necas, Slovak University of Technology in Bratislava (Slovakia)
Radioactive waste may arise throughout the lifetime of any type of nuclear facility. This waste has to be isolated from the environment
using the engineered and natural barriers of near surface or deep geological radioactive waste repository. Before final disposal,
the waste volume is reduced in the treatment process and then it is immobilized into the stable matrix.
In Slovakia, the treated radioactive waste is conditioned into fibre-reinforced concrete containers using a cementation technology.
<strong>The</strong>se containers are the only overpacks approved for near surface disposal in the National Radioactive Waste Repository located
at Mochovce nuclearsite (Slovakia). Every filled container has to fulfill the defined limits and conditions for safe transport and
disposal. <strong>The</strong> dose parameters, determining the safety of personnel handling a container, are one of them. Basically, the doses are
measured on the container walls` outer surfaces and on the lid of the container. <strong>The</strong> dose monitoring in 1 meter distance from the
container walls and from the lid of the container is performed before transportation as well.
<strong>The</strong> calculation code VISIPLAN 3D ALARA is a planning tool and it calculates dose parameters also for the above mentioned
positions concerning the fibre-reinforced concrete container which contains waste with different physical or radiological characteristics.
In the paper, calculated data are compared with in-situ measurements. Using VISIPLAN 3D ALARA planning tool, various
scenarios are evaluated. Finally, the Under the Global Partnership Initiative and in response to a Russian government request, the
Federal Government of Canada launched a program to dismantle Russian Federation Nuclear-Powered Submarines (NPS). In July
2004, Canada initiated a bilateral program for the dismantlement of 12 general purpose NPS in the Zvyozdochka shipyard in
Severodvinsk. Following successful completion of this program in March 2008, Canada initiated a second NPS dismantling program
at the Zvezda shipyard in the Russian Far East.
2) RISK ANALYSIS AND COST-BENEFIT ANALYSIS OF REMEDIAL ACTIONS
IN THE CENTRAL ASIA: AMYDARYA AND SYRDARYA RIVERS BASINS
TRANSBOUNDARY POLLUTION DUE TO URANIUM-MINING INDUSTRY - 16187
Vladimir Georgievskiy, Russian Research Center “Kurchatov Iinsitute” (Russia)
In this Report are considered some aspects of the analysis of consequences of uranium-mining industry in the Central Asia.
1. <strong>The</strong> risk analysis is considered in terms of collective effective commitment dose.
2. It is proposed the general estimation of risk (collective effective commitment dose) for the Central Asia from tailings piles
as a result of uranium mining in Kazakhstan, Uzbekistan, Kirghizia, and Tajikistan. This risk is the approximate estimate
of risk for Amydarya and Syrdarya Rivers Basins.
3. It is proposed the methodical approach to the analysis of risk dynamics (dose dynamic) for the talling piles accidents.
4. It is proposed theIt is proposed the analysis of the tailing piles remediation to carry out in terms cost-benefit analysis as
function of time
3) PARAMETRIC STUDIES FOR NUCLEAR CRITICALITY SAFETY USING MICROSOFT EXCEL - 16404
Michael Crouse, URS - Washington Division (USA)
An important piece of performing calculations for new or revised Nuclear Criticality Safety Evaluations often includes parametric
studies on one or more parameters of importance, e.g. mass or moderation level. Multiple input files may be generated quickly
for use in SCALE and potentially MCNP utilizing the Visual Basic for Applications (VBA) that is embedded within the Microsoft
Office — Excel program.
4) PROCESSING AND CONDITIONNING OF RADIOACTIVE SLUDGE - 16417
Olivier Lemaire, Bouygues Construction Services Nucléaires (France); Bertrand Lantes, EDF, (France);
Christophe LENagard,Bouygues Construction Services Nucléaires (France)
<strong>The</strong> EDF nuclear plants in operation include 58 pressurized water reactors, consisting of 34 units of 900 MWe, 20 of 1300
MWe and 4 of 1450 MWe.
In 2008, arisings of low and intermediate level waste, short live activity, packages amounted to 84.5 m3 /reactor. During the
same year, the plants in operation shipped 4,901m3 packs to the Aube repository centre, this volume included 108 m3 of concrete
containers containing intermediate level activity sludge.
<strong>The</strong> annual gross sludge volume produced per reactor ranges between about 1 and 2 m3 . This type of waste was not predicted
at the design stage of the reactors since it was assumed that the number of low porosity filtering steps in the water circuits would
be sufficient to trap any particles in suspension. <strong>The</strong> presence of sludge was verified after a few years of operation at the bottom of
sumps or tanks. Furthermore, allowance was not then made for the slow erosion of the concrete sumps nor for the fact that the tanks
collecting waste overflow could behave as chemical reactor enhancing co-precipitation phenomena.
EDF finalized in the eighties a sludge cementation process similar to the one utilised for conditioning evaporator concentrates
within concrete containers (processing of boric overflow). All the plants, according to their number of reactors, are equipped with
one or more facilities for waste encapsulation within a cementation matrix, but only the 900 MWe plants are able to condition both
evaporator concentrates and sludge.
80

Abstracts Session 22
SESSION 22 - POSTER SESSION - FACILITY DECONTAMINATION AND DECOMMISSIONING
A) BUILDING 18: OPERATING FEEDBACK FROM CLEANING AND DISMANTLING
OF GLOVE BOXES AND SHIELDING LINES - 16046
Michel Jeanjacques, Marie Pierre Bremond, Laurent Gautier,Guy Viellard,
Eric Pichereau, David Estivié, Commissariat l’Energie Atomique (France)
This summary presents the clean-up and dismantling works on glove boxes and shielded lines in building 18. <strong>The</strong> Atomic Energy
Commission’s centre at Fontenay Aux Roses (CEAFAR) was created in 1946. A radiochemical laboratory devoted to R&D programs
focused on studies of irradiated fuel reprocessing processes, waste treatment processes and studies and production of
transuranic elements was built in the early 1960s. <strong>The</strong> R&D program was finally halted on 30 June 1995. <strong>The</strong> purpose of the building
18 clean-up program is to minimise the nuclear and traditional hazards and to reduce as much as possible the production of
high- and medium-level waste during subsequent dismantling work. <strong>The</strong> paper will deal with a short description of the operations
as well as the lessons learned and the feedback experience which could be of any help in on going or planned DD&R projects
B) AUTOMATED VEHICLE AND WASTE PACKAGE SURVEY SYSTEM - 16223
Arthur Desrosiers, Phillip Mann, Safety and EcologyCorporation (USA)
SEC provides radiological control services for the D&D of the K-25 Gaseous Diffusion Plant in Oak Ridge TN. <strong>The</strong> demolition
of the structure of the building has been initiated. Building debris will be disposed in a waste management facility on the Oak
Ridge Reservation. This will require an estimated 70,000 truck shipments and each truck shipment must be inspected for radiological
contamination. <strong>The</strong> inspection process includes measurements with hand held survey instruments and preparation of a clearance
ticket.We developed a system for automatically generating the clearance ticket in order to reduce costs. <strong>The</strong> system automates
data collection and report preparation by using a programmable handheld data terminal (HDT) that acquires the instrument readings
and prints a preformatted clearance ticket. We estimate that the number of labor hours required to perform these truck inspections
will be reduced by 33% compared to previous methods.
<strong>The</strong> key to success for this project was developing a simple software interface that provides a graphic diagram of the truck and
the survey points, provides step-by-step directions and status during the inspection, and enters data onto a preformatted report that
can be printed directly from the HDT. Symbols differentiate the contact and smear measurements. <strong>The</strong> inspector simply positions
the instrument probe and presses a button on the HDT to acquire data. <strong>The</strong> HDT software evaluates each measurement and instructs
the inspector to continue taking measurements or respond to elevated levels of contamination. When the survey is completed, the
HDT provides a clearance message on the LCD screen and the inspector may proceed to the next truck survey. At the end of the
work turn, the stored results are printed for review and signature. Although the time required to complete the measurements is not
reduced, the time required to prepare documentation is drastically condensed. Although the initial implementation is limited to surveying
large trucks, the process may be extended to any repetitive waste management survey, such as inspections of shipping packages.
Future versions of the software may also be expanded to minimize the time required for each measurement.
C) TECHNICAL PERFORMANCE CHARACTERIZATION OF FOURIER TRANSFORM PROFILOMETRY FOR
QUANTIATIVE WASTE VOLUME DETERMINATION UNDER HANFORD WASTE TANK CONDITIONS - 16281
David Monts, Ping-Rey Jang, Zhiling Long, Olin Norton,
Walter Okhuysen, Yi Su, Charles Waggoner, Mississippi State University (USA)
<strong>The</strong> Hanford Site in western Washington state is currently in the process of an extensive effort to empty and close its radioactive
single-shell and double-shell waste storage tanks. Before this can be accomplished, it is necessary to know how much residual
material is left in a given waste tank and the chemical makeup of the residue.
<strong>The</strong> Institute for Clean Energy Technology (ICET) at Mississippi State University is currently developing an quantitative intank
inspection system based on Fourier Transform Profilometry, FTP. FTP is a non-contact, 3-D shape measurement technique. By
projecting a fringe pattern onto a target surface and observing its deformation due to surface irregularities from a different view
angle, FTP is capable of determining the height (depth) distribution (and hence volume distribution) of the target surface, thus
reproducing the profile of the target accurately under a wide variety of conditions. Hence FTP has the potential to be utilized for
quantitative determination of residual wastes within Hanford waste tanks. We report the results of a technical feasibility study to
document the accuracy and precision of quantitative volume determination using the Fourier transform profilometry technique
under simulated Hanford waste tank conditions.
D) THE EMERGENCE OF SUSTAINABLE PRACTICE WITHIN DECOMMISSIONING - 16059
David Adamson, Sellafield Limited (UK); Jonathan Francis,University of Central Lancashire (UK)
Despite the advance of sustainable practice and energy efficient techniques outside of the nuclear industry, at the start of the
21st Century there was a lack of published guidance aimed at their adoption at specifically nuclear facilities. Even with the establishment
of the Nuclear Decommissioning Authority, there is very little guidance published on how to adopt sustainable practices
during decommissioning.
<strong>The</strong>re have been instances where energy efficiency had affected design and operations decisions. Projects aimed at responsible
housekeeping, switching off lights, and changes to the nuclear ventilation design philosophy illustrate a desire for action, but
these activities were championed by interested and motivated employees. Sustainable practice had not at that time received a strategic
lead that resulted in a management structure to enable a coordinated and concerted effort in sustainable practice. This paper
traces the progress during the 20th and early 21st Centuries, whereby sustainable practice is now established within a much firmer
foundation of case study, guidance and organisational structure; to embed sustainable practice within the United Kingdoms current
decommissioning programme. It looks at the development of relevant literature and, through interviews with key managers and
external stakeholders, demonstrates (i) the degree to which two essential guidance documents (the NiCOP and CIRIA SD:SPUR)
are permeating the industry, (ii) how the current work of the Characterisation and Clearance Group has evolved to influence the
decontamination and dismantling planning procedures and (iii) the transition from identifying free-release materials to actually
releasing them for re-use in the community.
81

Session 22 Abstracts
E) CFD STUDIES OF VORTEX AMPLIFIER DESIGN IN THE
CONTEXT OF SELLAFIELD NUCLEAR OPERATIONS - 16061
Martin J Birch, John Tyndall Institute for Nuclear Research (UK); Darren Parker, Land Securities Trillium (UK);
Jonathan Francis, University of Central Lancashire (UK); Raymond Doig, Sellafield Limited
<strong>The</strong> use of computational fluid dynamics (CFD) has had a substantial impact on the cost and nature of design studies involving
both external flows (e.g. aerofoils) and internal flowsthrough components (e.g. valve design); CFD packages are now used
extensively throughout the engineering community. <strong>The</strong> commercial software 'CFX' was used to conduct design studies of vortex
amplifier geometry. <strong>The</strong> use of the code has been validated by comparing the results of the simulations with experimental data. <strong>The</strong>
code is now being used to study changes to the geometry of the vortex amplifier that could not be reproduced experimentally at an
equivalent cost.
This paper reports on progress and current developments. <strong>The</strong> anomalous reverse flow in the supply ports of the mini-VXA
has been captured and the mixing in both the chamber and the precessing vortex core also appears to have been successfully reproduced.
F) DECOMMISSIONING OF A URANIUM CONVERSION PLANT AND
A LOW LEVEL RADIOACTIVE WASTE FOR A LONG TERM DISPOSAL - 16071
Yun D. Choi, D.S. Hwang, U.S. Chung, Korea Atomic EnergyResearch Institute (Korea)
In the middle of 2004, a decommissioning program for a conversion plant, which was constructed in 1982, and treated about
300 tons of natural uranium until it was shut down in 1992, obtained its approval of the regulatory body. Actual dismantling and
decontaminating activities have been performed since the July 2004 and will be terminated in December 2009.
<strong>The</strong> decommissioning works were mainly divided into two parts, for the inside of the building containing the process equipments
and for the lagoon sludges generated during the plant operation. <strong>The</strong> decommissioning for the inside of the building was carried
out by dismantling the process equipments, which were firstly segmented and decotaminated by a polishing and a washing with
steam and chemicals or a melting, and then a decontamination for the surfaces inside the building by scrabbling or grinding the
concrete walls. <strong>The</strong> decontamination goals were below 0.2Bq/g for the matallic segments and below 0.4Bq/g for the concrete walls.
A decontamination methods were selected according to the degree of contamination and a minimization of the low level radioactive
wastes was conducted throught the decommissioning works.
Lagoon sludge wastes had two types, one was an various inorganic nitrate salt mixture containing a very low concentration of
uranium, about 200~300ppm, in Lgoon-II and the other was an inorganic nitrate salt mixture containing a few percent of uranium
in Lagoon-I. To treat these sludge wastes a thermal decomposition facility was constructed and operated to produce stable sludge
wastes contained triuranium octoxides which are stable in the air. <strong>The</strong> final sludge wastes after a thermal treating for the sludge
waste of lagoon-I could be reused.
<strong>The</strong> final residual radioactivities for the inside of the building will be measured to cofirm a complete decontamination of the
uranium to back ground level and then the building will be considered for an other use.
G) REHABILITATION PROJECT FOR PODOLSK NONFERROUS METALS PLANT - 16136
Alexander V. Chesnokov, Victor G. Volkov, Anatoly Volkovich,Alexey Lemus,
Vitaly Pavlenko, Sergey Semenov, Russian Research Center “Kurchatov Institute”(Russia);
Maxim Gizay, Sergey Krahotkin, FSUE Federal Property Management Center (Russia)
Radioactive contamination of the site and facilities of Podolsk Nonferrous Metals Plant (PNMP) caused by unauthorized delivery
of a radioactive source among scrap metal to the plants melt shop refinery has occurred in 1989. As a result, the refinery premises
and adjacent territory, department of construction activity warehouse, internal railway branch, scrap metal site and two open
slag collectors were contaminated with 137Cs radionuclides.
Between 1989 and 2001, after site decontamination works, the waste belonging to MLW category was removed from the plants
operating zones and sent to MosNPO Radon for long-term storage. Waste belonging to LLW category was accumulated on several
dedicated sites and in the melt shop department. Secondary contamination of the internal railway branch and department of construction
activity warehouse took place as a result of decontamination activities.
It should be noted that no comprehensive engineering and radiation survey of contaminated facilities and site of PNMP has
ever been performed. Though the contaminated area is situated in the immediate vicinity of the Petritsa River, and there is a risk of
its contamination with radionuclides, no comprehensive study of radionuclide contents in subsurface and ground waters, as well as
no radionuclide migration study, has been performed.
In 1992-1993, Federal State Unitary Enterprise State Specialized Design Institute(FSUE SSDI) has developed a work project
entitled Elimination of radioactive contamination consequences and interim radwaste repository construction at PNMP. <strong>The</strong> project
was updated in 1997, 2001 and 2005. It provided for constructing a regional on-site interim radwaste repository at the PNMP
site.
H) REMOTE RADIATION SENSOR BASED ON EPOXY RESIN AND OPTICAL
FIBER FOR MONITORING OF HIGH-LEVEL DECOMMISSIONING FACILITIES - 16160
Bum-Kyoung Seo, Chan-Hee Park, Dong-Gyu Lee, Kune-Woo Lee, Korea Atomic Energy Research Institute (Korea)
It’s important to survey the radiation level in the nuclear facilities to be decommissioned. In some facilities such as hot-cell the
radiation level is very high. So it is difficult to approach for monitoring the radioactive contamination. In this case the detector system
is preferable to separate the sensor and electronics, which have to locate in the facility outside to avoid the electric noise and
worker’s exposure.
In this study the remote radiation sensor for radiation and contamination monitoring of the decommissioning facility was developed.
<strong>The</strong> radiation sensor was prepared using a transparent epoxy resin and a scintillator. <strong>The</strong> used scintillators were an organic
for gamma-rays and inorganic one for alpha particles.
82

Abstracts Session 22
<strong>The</strong> powder type organic scintillator was mixed with the optically transparent epoxy resin until the powder was completely wet
and uniformly distributed throughout the liquid. <strong>The</strong> mixture was then poured into a polyethylene mold and cure into a bulk type.
<strong>The</strong> used organic scintillator was 2,5-diphenyloxazde (PPO) as a first solute and 1,4-bis[5-phenyl-2-oxazol]benzene (POPOP) as a
second solute which was a wave shifter. Also, the inorganic scintillator ZnS(Ag) was used for measuring the alpha particles. <strong>The</strong>
powder type ZnS(Ag) was mixed with the epoxy resin, and then solidified.
For remote measurement the optical fiber was used. <strong>The</strong> scintillation light produced by interaction with the radiation and scintillator
was transmitted through an optical fiber to the photon counter that is placed in the high-level radiation area outside. <strong>The</strong>
optical fiber was inserted into the radiation sensor before solidification of the epoxy resin, and then solidified. <strong>The</strong> remote radiation
sensor was the one-body type with the scintillation detector and the optical fiber. <strong>The</strong> ability of the radiation detection and the
signal transmission were tested.
I) ALGORITHMISATION OF DISMANTLING TECHNIQUES IN
STANDARDISED DECOMMISSIONING COSTING - 16201
Peter Bezak, DECOM, a.s. (Slovakia); Vladimír Daniaka,Deconta, a.s.(Slovakia);
Ivan Rehak, Decom, a.s. (Slovakia); Vladimir Necas, Slovak University of Technology in Bratislava(Slovakia)
Recently developed computer code OMEGA for evaluation and optimisation of decommissioning options implements the standardised
cost structure (IAEA, OECD/NEA, EC, 1999) as the universal structure [PSL] for calculation and optimisation of decommissioning
scenarios. One of the groups of decommissioning activities is the dismantling of systems and structures. <strong>The</strong>se activities
variously depend on the complexity of dismantled systems, e.g. reactors, equipment of the primary systems or standard components
like pipes, valves, motors, tanks etc. Type and extent of decommissioning activities depends also on local conditions for
dismantling like dose rate, decommissioning equipment category, local working conditions, etc. <strong>The</strong>se factors determine the selection
of techniques for dismantling, depending on material and radiological status of the equipment (type of technique and their manual
or remote application). This approach enables proper planning and performing of individual decommissioning phases.
J) THERMAL CUTTING TECHNOLOGIES FOR DECOMMISSIONING OF NUCLEAR FACILITIES - 16297
Harald Bienia, NUKEM Technologies GmbH (Germany)
Remote disassembly of radiologically burdened large components is among the most sophisticated and complex activities in
the dismantling of nuclear installations. High local dose rates and contamination levels, combined with complicated designs and
geometries of the object to be dismantled, plus insufficient accessibility, imply major challenges in the dismantling of nuclear facilities.
Usually the shielding effect of water is used during the dismantling period. Other dismantling activities require dry ambiences.
<strong>The</strong> required space for the technical equipment during the dismantling operations, especially for the removal of larger components
(e.g. reactor pressure vessel, heat exchanger, etc.) is often an additional problem. Conventional cutting technologies like sawing
with a disk saw or band saw require large and heavy frameworks as well as guiding systems with high rigidity. <strong>The</strong>se solutions
are expensive and sometimes not applicable.
Additionally these technical questions, the estimated costs of the used dismantling technologies are important for choosing the
best cutting technology. <strong>The</strong> three cutting technologies Autogenous Flame Cutting, Plasma Arc Cutting and Contact Arc Metal Cutting
are proven tools for dismantling tasks and will be introduced.
K) INVOLVEMENT OF ANDRAD IN ENDORSEMENT OF DECOMMISSIONING
DOCUMENTATION OF NUCLEAR FACILITIES IN ROMANIA - 16315
Marin Dinca, National Agency for Radioactive Waste (Romania)
National Agency for Radioactive Waste ANDRAD is in Romania, by law, the competent authority for the disposal administration
of spent nuclear fuel and radioactive waste and for the coordination of the predisposal management of spent nuclear fuel and
radioactive waste, inclusive decommissioning of nuclear facilities.
Government Ordinance (GO) No. 11/January 30, 2003 and Government Decision (GD) No. 1601/December 23, 2003 established
the ANDRAD’s foundation and organization.
In accordance with GO No. 11/2003, republished, on the safe management of the radioactive waste, ANDRAD has the responsibility
to endorse the decommissioning documentation issued by the main radioactive waste generators (nuclear installations and
other major radiological installations: radioactive waste treatment plants, radioactive waste storage facilities, post irradiation examination
laboratories, centres for radioisotopes production etc.).
ANDRAD receives for endorsement some of the documentation for decommissioning that is provided by enforced norms for
each type of nuclear facility.
<strong>The</strong>re are presented the nuclear facilities that must have decommissioning documentation endorsed by ANDRAD, the type of
documents submitted by license holder to ANDRAD and the procedure of endorsement in relation with the regulatory body
(CNCAN) approval of the decommissioning documents.
L) VISUALIZATION OF RADIOACTIVE SOURCES WITHOUT
GAMMA-RADIATION WITH UV IMAGING SYSTEMS - 16145
Oleg Ivanov, Alexey Danilovich, Vyacheslav Stepanov, SergeySmirnov, RRC Kurchatov Institute (Russia);
Anatoly Volkovich, Russian Research Center “Kurchatov Institute”, (Russia)
New UV cameras are suitable for imaging of α-contamination by fluorescence of atmospheric air the near ultraviolet (wavelength
– 280 – 390 nm) region.<strong>The</strong>ir parameters are: FOV for detecting in UV spectral region is 8” x 6”. <strong>The</strong> optical FOV is about
48” x 36” . DayCor SUPERB UV camera has sensitivity 3x10-18 W/cm2 enables detection and displaying corona emission as weak
as 1.5 pC at distance 8 m, and capture moving targets without smearing the output image. Instruments sensitivity for alpha contamination
registration in terms of minimum measurable activities (MMA) have been estimated as, 40 – 100 Bq/cm2 (measurement
time is 3600 – 600 sec correspondently).
83

Session 22-24 Abstracts
M) OXIPROBE — A NON DESTRUCTIVE TOOL FOR DETERMINING STEAM
GENERATOR OXIDE CHARACTERISTICS - 16250
John P., Krasznai, Kinectrics Inc. (Canada)
CANDU Stations are designed with significant amounts of carbon steel piping in the primary circuit. Although the primary
coolant chemistry is such that carbon steel corrosion is minimized, nevertheless magnetite transport from the carbon steel surfaces
to the steam generators is a significant issue leading to potential reduction in heat transfer efficiency in the steam generator. <strong>The</strong>re
are other contributors to the reduction of heat transfer efficiency such as divider plate leakage whereby some of the coolant short
circuits the steam generator tubes and secondary side steam generator tube fouling.
CANDU station operators have utilized a number of mitigating measures such as primary and secondary side mechanical and
chemical tube cleaning, and divider plate refurbishment to counter these problems but these are all expensive and dose intensive,
It is therefore very important to establish the relative contribution of each source to the overall heat transfer degradation problem
so the most effective results are obtained. Tube removal and laboratory assessment of the oxide loading is possible and has been
utilized but at best it provides an incomplete picture since typically only short lengths of tubes are removed most often from the
hot leg and the tube removal process adversely impacts the primary side oxide integrity. Kinectrics Inc. has developed, qualified
and deployed Oxiprobe, a highly mobile non destructive technology cable to remove and quantify the deposited oxide loading on
the primary surfaces of steam generator tubes. <strong>The</strong> technology is deployed during shutdown and provides valuable, direct information
on:
• Primary oxide distribution within the steam generator
• Oxide loading (thickness of oxide) on the primary surfaces of steam generator tubes
• Oxide composition and radiochemical characterization
N) METHODS OF CONTROL OF INACCURACY IN CALCULATION OF NUCLEAR POWER PLANT
DECOMMISSIONING PARAMETERS - 16383
Frantisek Ondra, DECOM, a.s.,(Slovakia); Vladimír Daniaka, Deconta, a.s.,(Slovakia) Ivan Rehak, Decom, a.s.,
(Slovakia);Vladimir Necas, Slovak University of Technology in Bratislava(Slovakia)
<strong>The</strong> aim of the article is a development of analytical methodology for evaluation of input data inaccuracies impact on calculation
of cost and other output decommissioning parameters. This methodology is based on analytical model calculations using the
OMEGA code and taking into account the probability of input data inaccuracies occurrence also.
SESSION 23 - PANEL: CURRENT IAEA ACTIVITIES IN PREDISPOSAL
MANAGEMENT OF L/ILRADIOACTIVE WASTE
ABSTRACTS NOT REQUIRED
SESSION 24 - NATIONAL AND INTERNATIONAL D&D PROGRAMS
1) DECOMMISSIONING IN THE UNITED STATES - PAST, PRESENT AND FUTURE - 16318
Jas S. Devgun, Sargent & Lundy (USA)
<strong>The</strong> experience related to decommissioning of nuclear facilities in the United States is very substantial and covers power reactors,
research reactors, and many facilities in the Department of Energy complex. <strong>The</strong> focus of this paper however is on the commercial
power plants.
With 104 operating reactors, the U.S. fleet of civilian reactors is still the largest in the world. Nuclear power industry in the
United States has undergone a dramatic upturn after decades of stalemate. One effect of this nuclear renaissance has been that the
plans have changed for several reactors that were initially destined for decommissioning. Instead, the focus now is on relicensing
of the reactors and on power uprates. In fact, after the peak period between 1987 and 1998, no additional power reactors have been
shutdown. On the contrary, power uprates in the past twenty years have added a cumulative capacity equivalent to five new reactors.
Almost all the operating reactors plan to have license extensions, thus postponing the eventual decommissioning.
Nevertheless, in addition to the 9 reactors where licenses have been terminated following decommissioning, 12 power and
early demonstration reactors and 14 test & research reactors are permanently shutdown and are in decommissioning phase. Substantial
experience and lessons learned are available from the U.S. projects that are of value to the international decommissioning
projects, especially where such projects are in early stages. <strong>The</strong>se lessons cover a wide array of areas from decommissioning plans,
technology applications, large component removal, regulatory and public interface, decommissioning funding and costs, clean up
criteria, surveys of the decommissioned site, and license termination. Additionally, because of the unavailability of a national spent
fuel disposition facility, most decommissioning sites are constructing above ground interim storage facilities for the spent nuclear
fuel.
2) DECOMMISSIONING STRATEGIES WORLDWIDE: A RE-VISITED OVERVIEW
OF RELEVANT FACTORS - 16016
Michele Laraia, <strong>International</strong> Atomic Energy Agency (IAEA) (Austria)
This paper highlights current trends and developments in selecting decommissioning strategies worldwide. Radiological conditions,
spent fuel and radioactive waste management, funding, economics and the development of suitable technology are some
common factors for taking decisions on the timing and circumstances of decommissioning. Although safe enclosure is the selected
option for many shut down facilities typically due to lack of ready cash, delay in dismantling may have serious disadvantages
such as loss of expertise and long term uncertainties.
84

Abstracts Session 24
Currently, of the many large nuclear installations permanently shut down, only a fraction have been or will be in the near term
totally dismantled and decommissioned to unrestricted release state. A trend towards immediate dismantling seems to emerge in
some countries, and is supported by IAEA positions, but this appears to be due to country-, site- or plant-specific conditions of limited
generic applicability.
In recent years, and often as the result of international efforts, the situation is evolving and provisions and infrastructures
including funding are being established to cope with decommissioning challenges. This factor seems in principle to encourage
immediate, total dismantling. However, the worldwide overview of decommissioning strategies does not offer a clear pattern. New
factors have come into being, such as stakeholder opinions, in particular those of local communities, and now play a significant
role in decision-making. <strong>The</strong> conditions of the nuclear industry at large (e.g. the nuclear renaissance) have considerably changed
over the last few years and are going to affect decommissioning. Strategies such as restricted release (brownfields), incremental
decommissioning or entombment seem to offer new prospects. <strong>The</strong> author reviewed the worldwide situation around the year 2000,
and offers in this paper some reflections about changed worlds conditions and how these affect the decommissioning scenarios.
3) A NATIONWIDE MODELLING APPROACH TO DECOMMISSIONING - 16182
Bernard Kelly, University of Manchester (UK); Paul E Mort,Sellafield Ltd. (UK);
Andrew J Lowe, University of Manchester (UK)
In this paper we describe a proposed UK national approach to modelling decommissioning. For the first time, we shall have
an insight into optimizing the safety and efficiency of a national decommissioning strategy. To do this we use the General Case
Integrated Waste Algorithm (GIA), a universal model of decommissioning nuclear plant, power plant, waste arisings and the associated
knowledge capture. <strong>The</strong> model scales from individual items of plant through cells, groups of cells, buildings, whole sites and
then on up to a national scale. We describe the national vision for GIA which can be broken down into three levels:
1) the capture of the chronological order of activities that an experienced decommissioner would use to decommission any
nuclear facility anywhere in the world this is Level 1 of GIA;
2) the construction of an Operational Research (OR) model based on Level 1 to allow rapid what if scenarios to be tested
quickly (Level 2);
3) the construction of a state of the art knowledge capture capability that allows future generations to learn from our current
decommissioning experience (Level 3).
We show the progress to date in developing GIA in levels 1 & 2. As part of level 1, GIA has assisted in the development of an
IMechE professional decommissioning qualification. Furthermore, we describe GIA as the basis of a UK-Owned database of
decommissioning norms for such things as costs, productivity, durations etc. From level 2, we report on a pilot study that has successfully
tested the basic principles for the OR numerical simulation of the algorithm. We then highlight the advantages of applying
the OR modelling approach nationally. In essence, a series of what if&scenarios can be tested that will improve the safety and
efficiency of decommissioning.
4) IMPLEMENTATION AND ONGOING DEVELOPMENT OF A COMPREHENSIVE PROGRAM
TO DEAL WITH CANADAS NUCLEAR LEGACY LIABILITIES - 16039
Douglas Metcalfe, Pui Wai Yuen, David McCauley, Natural Resources Canada (Canada);
Sheila Brooks, Joan Miller, Michael Stephens, Atomic Energy of Canada Limited (Canada)
Nuclear legacy liabilities have resulted from 60 years of nuclear research and development carried out on behalf of Canada by
the National Research Council (1944 to 1952) and Atomic Energy of Canada Limited (AECL, 1952 to present). <strong>The</strong>se liabilities
are located at AECL research and prototype reactor sites, and consist of shutdown reactors, research facilities and associated infrastructure,
a wide variety of buried and stored waste, and contaminated lands.
In 2006, the Government of Canada adopted a new long-term strategy to deal with the nuclear legacy liabilities and initiated
a five-year, $520 million (Canadian dollars) start-up phase, thereby creating the Nuclear Legacy Liabilities Program (NLLP). <strong>The</strong>
objective of the long-term strategy is to safely and cost-effectively reduce risks and liabilities based on sound waste management
and environmental principles in the best interests of Canadians. <strong>The</strong> five-year plan is directed at addressing health, safety and environmental
priorities, accelerating the decontamination and demolition of shutdown buildings, and laying the groundwork for future
phases of the strategy. It also includes public consultation to inform the further development of the strategy and provides for continued
care and maintenance activities at the sites.
<strong>The</strong> NLLP is being implemented through a Memorandum of Understanding between Natural Resources Canada (NRCan) and
AECL whereby NRCan is responsible for policy direction and oversight, including control of funding, and AECL is responsible for
carrying out the work and holding and administering all licences, facilities and lands.
5) THE SWEDISH PROGRAM FOR FUTURE D&D OF NUCLEAR POWER PLANTS - 16143
Jan Carlsson, Swedish Nuclear Fuel and Waste Management Co (SKB) (Sweden)
According to Swedish law anyone who has a license for a business in which radioactive waste is arising also has the responsibility
to make sure the waste is safely handled and disposed of. <strong>The</strong> major radioactive waste producers in Sweden are the Nuclear
Power Plants. <strong>The</strong> owners of the NPPs have jointly formed the Swedish Nuclear Fuel and Waste Management Company, SKB, to
take care of their radioactive waste in a safe and economical way. In the facilities and systems built and operated by SKB also
radioactive waste from other, small, waste producers are accepted.
<strong>The</strong> 12 Swedish Nuclear Power Reactors are located at four sites. <strong>The</strong> reactors at one site, Barsebäck, have been shut down for
political reasons after about 25 years of operation while reactors at the other three sites are planned for 50 to 60 years of operation.
<strong>The</strong> basic decommissioning strategy is an early dismantling after the final shut down. One request is that a final repository for short
lived decommissioning waste shall be available before any major dismantling begins. A project for extension of the existing SFR
repository is in progress and the extension is expected to be in operation the year 2020. <strong>The</strong> first reactors to be dismantled are the
reactors at Barsebäck. Also already shut down and ready for dismantling are two small reactors, Ågesta in Stockholm and a research
reactor at the Studsvik site. <strong>The</strong> other reactors will be decommissioned from around the year 2030.
85

Session 24-25 Abstracts
6) AREVA DECOMMISSIONING STRATEGY AND PROGRAMME - 16036
Guy Decobert, AREVA (France) Arnaud Gay, AREVA NC (France)
This article is about AREVAs nuclear site dismantling strategy and the presentation of the recent Nuclear Site Value Development
Business Unit main tasks and its projects Created beginning of 2008, this business unit is aimed at the dismantling of the back
end fuel cycle installations. It gathers four main projects : a reprocessing plant UP2 400 on AREVA La Hague site, an other reprocessing
plant UP1 on CEA Marcoule site, a MOX fuel plant on Cadarache and two GCR fuel fabrication plants located on Veurey
and Annecy sites.
<strong>The</strong> main objectives of this business unit are to enhance the feed-back, to contribute to performance improvements, to value
professionals and to put innovation forward.<strong>The</strong>se emerging activities constitute a major know-how for AREVA and will increase
overtime.
7) NUCLEAR POWER PLANT DECOMMISSIONING IN GERMANY -
PROJECTS, REGULATION AND EXPERIENCE - 16359
Leopold Weil, Federal Office for Radiation Protection (BfS) (Germany);
Bernd Rehs, Federal Office for Radiation Protection (Germany)
In Germany, altogether 19 nuclear power plants (NPPs) and prototype reactors have been permanently shut down. For 15 NPPs
the dismantling is in progress with green-field conditionsas planning target. Two units were completely dismantled and two are in
safe enclosure.
<strong>The</strong> main legal provision for all aspects of the peaceful use of nuclear energy in Germany is the Atomic Energy Act (AtG),
which also contains the basic legal conditions for the decommissioning of nuclear facilities. It stipulates that decommissioning is
subject to a licence by the regulatory body of the respective Federal State (Land).
An emerging decommissioning practice in Germany is the removal of complete undismantled large components and their transport
to interim storage facilities. During the period of storage, the radionuclide inventory of the components will decrease due to
radioactive decay and the subsequent segmentation of the components can be done with less radiation protection effort.
<strong>The</strong> commissioning of the Konrad repository in the near future might have consequences on planning of decommissioning,
regarding the selection of a decommissioning strategy and the waste management.
6) VARIATION OF LIGHT WATER REACTOR DECOMMISSIONING STRATEGIES IN JAPAN - 16113
Takeshi Ishikura, Shigenbu Hirusawa, <strong>The</strong> Institute of Applied Energy (Japan);
Yoshihiko Horikawa, <strong>The</strong> Kansai Electric Power Company (Japan)
<strong>The</strong>re are 55 light water reactors (LWRs) in operation in Japan. Nuclear reactor decommissioning has already started with
Tokai GCR and Fugen heavy water cooled reactor. It is assumed in 2030s that numbers of LWRs start decommissioning year after
year in Japan, supposing that LWRs plant life is 60 years. We should, however, early prepare LWR decommissioning because its
schedule can be accelerated, as exampled by Hamaoka 1&2 BWR which was announced in December 2008 to permanently shut
down.
Japan has carefully prepared for reactor decommissioning in policy, regulation and technology since 1980s. A basic view
including a standard decommissioning process on commercial nuclear power plants was initially proposed by a committee of Ministry
of <strong>International</strong> Trade and Industry (MITI, currently Ministry of Economy, Trade and Industry, METI) in 1985, in which short
safe storage scenario with early dismantling was recommended in consideration of future site reuse. In 1990, a law on nuclear
power plant dismantling cost reservation was established based on the IAEs cost estimation. In 1987-2004, the former NUPEC had
implemented comprehensive decommissioning technology development. In 2001, a METI committee recommended that the safe
storage period should be flexible depending on site specific condition. In 2005, the law for the regulation of nuclear source material,
nuclear fuel material and reactors (LRNR) was amended to regulate concrete decommissioning procedure including decommissioning
plan to be submitted for regulatory permit. Now it is time for related parties to prepare actual decommissioning strategy
for LWRs.
SESSION 25 - TREATMENT, MANAGEMENT AND RECYCLE OF D&D MATERIALS
1) WASTE REDUCTION BY RE-USE OF LOW ACTIVATED MATERIAL - 16035
Ulrich Ehrlicher, Heinz Pauli, Paul Scherrer Institut (Switzerland)
A multidisciplinary institute, equipped with research reactors and accelerator-driven research installations produces and, in the
case of PSI, collects radioactive waste on one hand and requires material, especially for shielding purpose, on the other hand. <strong>The</strong>
legislative framework for radiation protection, financial reasons and limited storage capacity strongly force Paul Scherrer Institute
and comparable facilities to minimize radioactive waste. Besides free release of inactive components, recycling and re-use of lowlevel
radioactive material in controlled areas are the best means for waste minimization. <strong>The</strong> re-use of slightly activated steel plates
as a shielding material and the recycling of irradiated reactor graphite as a filling material embedded in mortar may give examples
and encouragement for similar activities. Besides the advantages for radiation protection, the financial benefit can be measured in
millions of dollars.
2) ANALYTICAL METHODOLOGY FOR OPTIMIZATION OF WASTE MANAGEMENT SCENARIOS
IN NUCLEAR INSTALLATION DECOMMISSIONING PROCESS - 16148
Matej Zachar, Slovak University of Technology in Bratislava (Slovakia);
Vladimir Daniska, Deconta, a.s. (Slovakia); Ivan Rehak, Marek Vasko, Decom, a.s.(Slovakia);
Vladimir Necas, Slovak University of Technology in Bratislava (Slovakia)
<strong>The</strong> nuclear installation decommissioning process is characterized by production of large amount of various radioactive and
non-radioactive waste that have to be managed, taking into account their physical, chemical, toxic and radiological properties.
Waste management is considered to be one of the key issues in the frame of the decommissioning process.
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Abstracts Session 25-26
During the decommissioning planning period, the scenarios covering possible routes of materials release into the environment
and radioactive waste disposal, should be discussed and evaluated. Unconditional and conditional release to the environment, longterm
storage at the nuclear site, near surface or deep geological disposal and relevant material management techniques for achieving
the final status should be taken into account in the analysed scenarios. At the level of the final decommissioning plan, it is
desired to have the waste management scenario optimised for local specific facility conditions taking into account a national decommissioning
background.
<strong>The</strong> analytical methodology for decommissioning waste management scenarios evaluation, presented in the paper, is based on
the materials and radioactivity flow modelling which starts from waste generation activities like pre-dismantling decontamination,
selected methods of dismantling, waste treatment and conditioning, up to materials release or conditioned radioactive waste disposal.
Necessary input data for scenarios, e.g. nuclear installation inventory database (physical and radiological data), waste processing
technologies parameters or material release and waste disposal limits, has to be considered. <strong>The</strong> analytical methodology principles
are implemented into the standardised decommissioning parameters calculation code OMEGA, developed in the DECOM
company. In the paper the examples of the methodology for the scenarios optimization are presented and discussed.
3) CHARACTERISATION OF RACTOR GRAPHITE TO INFORM STRATEGIES FOR
DISPOSAL OF REACTOR DECOMMISSIONING WASTE - 16389
Andrew Hetherington, Phil Davies, NDA (UK)
Graphite has been used extensively as a neutron moderator and reflector in reactors in the UK since the 1950s. <strong>The</strong> UK nuclear
decommissioning programme will result in some 90,000 tonnes of waste graphite being removed. A number of other countries also
have graphite reactors scheduled for decommissioning, but UK has the largest graphite waste liability of any.
<strong>The</strong> current UK baseline strategy, which is to package graphite waste and then consign it to geological disposal is considered
feasible, but it has not yet been shown to represent the optimum solution in terms of cost, safety and protection of the environment.
<strong>The</strong> NDA is currently engaged in investigating alternative solutions for reactor graphite. A review of worldwide developments has
enabled a decision chart to be compiled for managing graphite waste showing, at a high level, the strategic options and processes
needed to take the graphite from a shut?down reactor, to the point where it is finally disposed of.
Physical characterisation is needed to provide a detailed radionuclide inventory for the graphite to supplement theoretical calculations.
Such an inventory, together with information about the physical and chemical characteristics of the material is a prerequisite
for making decisions about its interim management as well as final disposition. <strong>The</strong>re is a need to progress understanding of
uncertainties in the activity of the long?lived radionuclides in graphite and of particular significance is precise characterisation in
relation to Carbon?14 and Chlorine?36. Using information about the impurity levels in graphite at the various sites along with irradiation
history, modelling tools will be used to assess the profile of key radionuclides within the graphite with a view to optimising
the disposal route.
4) DEMONSTRATION OF UK ILW TREATMENT BY GEOMELT VITRIFICATION - 16105
Keith Witwer, Kevin Finucane, Eric Dysland, AMEC, GeoMelt Division (USA)
Experiments for airborne dispersion ratio of radionuclides during plasma arc cutting were carried out in a contamination control
enclosure, using stored radioactive metal wastes arising from the decommissioning activities of Japan Power Demonstration
Reactor, which was a boiling water type reactor. Neutron induced-activated piping and surface contaminated piping were segmented
into pieces using air plasma arc cutting, using a current power was 100A. In addition, similar experiments for contaminated piping
of the Advanced <strong>The</strong>rmal Reactor, Fugen were carried out.
As a result, dispersion ratios for activated piping were 0.2 to 0.7% of Co-60 and 0.4% of Ni-63 under the condition with a covered
cap on the head. And those for surface contaminated piping were from 18 to 23%. In addition, those for vertically segmented
piping which simulated flat plate were from 34 to 43%. <strong>The</strong>re was no difference of dispersion ratios between stainless steel and
carbon steel base materials. All values obtained were smaller than the Handbook recommended value of 70% for contaminated
materials.
Filtering collection efficiencies of the coarse dust filter were approximately 40% for activated piping and approximately 55 to
80 % for surface contaminated piping. However there was no effect for collection of aerosols smaller than 1μm.
Size distribution analysis indicated a greater concentration of radionuclides in particles smaller than 0.1μm when compared
with larger particles. In addition, there was a tendency that the Ni-63 was concentrated to the particles smaller than 0.3μm compared
with the Co-60.
<strong>The</strong> results support data obtained in the previous studies using non-radioactive materials.
SESSION 26 - D&D UPDATE AND MANAGEMENT ISSUES
1) RENEWING THE FOCUS ON DECOMMISSIONING: BRINGING A NEW
MANAGEMENT PERSPECTIVE TO SELLAFIELD - 16243
Russ A Mellor, Sellafield Ltd (UK)
Sellafield site, on the West Coast of Cumbria, has recently emerged from a long competition process with new Parent Body
Organisation Nuclear Management Partners taking the helm of the UK nuclear industry flagship.
Bringing together three major companies, URS Washington Division, AREVA and AMEC, all leaders in their fields, NMP
bring a new perspective to the way the Sellafield site is managed, using an approach that focuses on three Ps People, Partnership
and Performance.
Following a restructure of the company, one of the key drivers for future lifetime plans is that of handling the legacy waste and
a major reorganisation of the site led to the evolvement of two distinct arms, Projects and Support. Sitting within Projects, and
evolved from the Nuclear Decommissioning and Major Projects Group, the Clean-up directorate look after four key areas; Contaminated
land, Legacy Ponds & Silos, Windscale and Decommissioning & Waste.
<strong>The</strong> paper will look in more depth at
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Session 26 Abstracts
• <strong>The</strong> benefits to Sellafield Ltd from working with NMP partner companies; How the ability to draw on skills and technical
knowledge from other world leading companies will help meet the challenges faced by the site
• <strong>The</strong> benefits of the reorganisation for the company; How the initial change programme has impacted on operational effectiveness
• <strong>The</strong> advantages of applying a People, Partnering and Performance approach; How clearly defined expectations form the
basis for NMPs management strategy
• Opportunities for the supply chain; how the emphasis on Partnership will maximise working opportunities for the supply
chain, and how it will be made easier to work with Sellafield
• Looking forward to the future; how Sellafield Ltd will be positioned to seize whatever opportunities may arise from future
decisions by the UK government about potential new nuclear missions
2) EMBEDDING NUCLEAR, ENVIRONMENTAL AND SAFETY MEASURES FROM
DESIGN THROUGH TO DECOMMISSIONING - 16212
Jack Williamson, Sellafield Ltd, Seascale (UK)
A key part of the UK nuclear industry for more than five decades, Sellafield represents the most challenging nuclear site management
programme in the world
Originally, established during the early 1940s to home Royal Ordnance factories producing explosives for World War II, today
Sellafield Ltd manages and operates the West Cumbrian site on behalf of its owners, the Nuclear Decommissioning Authority.
Activities centre on remediation, decommissioning, accelerated hazard reduction and clean-up of the historic legacy, however the
site is also home to a number of commercially operated plants, including the Thorp and Magnox reprocessing plants, the Sellafield
Mixed Oxide Fuel manufacturing plant and a range of waste management and effluent treatment facilities
Sellafield Ltds Nuclear Decommissioning and Major Project Group is responsible for managing all of the current and future
decommissioning work and major build projects on the site, a programme valued at approximately £46 billion
Nuclear Safety is the overriding priority for the group, and inspiring confidence in new nuclear facilities is seen as playing an
important role in any future nuclear renaissance.
Looking at both radiological and conventional safety, this paper will discuss the importance of embedding safety into all phases
of the nuclear new build programme; Design, Construction, Commissioning and Decommissioning. It will also look at how
adopting a partnership approach between all parties involved in the build process can not only maximise conventional safety and
realise the design intent but also minimise waste when the plant is eventually decommissioned.
3) OPTIMISING THE UK WASTE MANAGEMENT PROGRAMME USING INVENTORY MODELING - 16394
Mervin McMinn, NDA(USA)
<strong>The</strong> UK updates the National Inventory of radioactive waste every three years. <strong>The</strong> latest iteration, based on a stock date of
April 2007, was published in May 2008. At that time, there were approximately 1,300 identified waste streams representing 290,000
m3 of L/ILW already in stock, with an additional 3,100,000 m3 forecast future lifetime arisings. Under the current baseline Strategy,
around 90% of the arisings are destined for a low level waste repository (LLWR) with the remaining 380,000 m3 destined for
a geological disposal facility (GDF).
<strong>The</strong> data in the National Inventory is used to support and underpin the L/ILW Strategic Design Authorities (SDA) in developing
alternative waste management Strategic Options. One significant business driver is to identify opportunities for reducing the
volume of waste for geological disposal, Inventory modelling quantifies the benefits that would be obtained by adopting alternative
waste treatment solutions.
This paper sets out the current scope of the UK National Inventory and the process and tools employed to compile a validated
dataset. Strengths and weaknesses of the current approach will be highlighted. Areas targeted for improvement will be outlined,
including reducing the uncertainty in the data and improving the lead-time for publishing an approved report. <strong>The</strong> future scope and
expected benefits will be described, in particular proactive modelling of the value of alternative waste management options and a
more data-driven approach to developing an optimised National Integrated Waste Strategy. In closing, the paper will illustrate the
modelled impact of strategic options that are being considered for further development.
4) INNOVATIVE HIGHLY SELECTIVE REMOVAL OF CESIUM AND STRONTIUM UTILIZING A NEWLY
DEVELOPED CLASS OF INORGANIC ION SPECIFIC MEDIA - 16221
Mark Denton, Kurion, Inc., (USA) Dr. Mercouri Kanatzidis, Northwestern University (NWU) (USA)
Highly selective removal of Cesium and Strontium is critical for waste treatment and environmental remediation. Cesium-137
is a beta-gamma emitter and Strontium-90 is a beta emitter with respective half-lives of 30 and 29 years. Both elements are present
at many nuclear sites. Cesium and Strontium can be found in wastewaters at Washington State’s Hanford Site, as well as in
wastestreams of many Magnox reactor sites. Cesium and Strontium are found in the Reactor Coolant System of light water reactors
at nuclear power plants. Both elements are also found in spent nuclear fuel and in high-level waste (HLW) at DOE sites. Cesium
and Strontium are further major contributors to the activity and the heat load. <strong>The</strong>refore, technologies to extract Cesium and Strontium
are critical for environmental remediation waste treatment and dose minimization.
Radionuclides such as Cesium-137 and Strontium-90 are key drivers of liquid waste classification at light water reactors and
within the DOE tank farm complexes. <strong>The</strong> treatment, storage, and disposal of these wastes represents a major cost for nuclear power
plant operators, and comprises one of the most challenging technology-driven projects for the DOE Environmental Management
(EM) program.
An alternative to these issues of organic ion-exchangers is emerging. Inorganic ion-exchangers offer a superior chemical, thermal
and radiation stability which is simply not achievable with organic compounds. <strong>The</strong>y can be used to remove both Cesium as
well as Strontium with a high level of selectivity under a broad pH range. Inorganic ion-exchangers can operate at acidic pH where
protons inhibit ion exchange in alternative technologies such as CST. <strong>The</strong>y can also be used at high pH which is typically found in
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Abstracts Session 27
conditions present in many nuclear waste types. For example, inorganic ion-exchangers have shown significant Strontium uptake
from pH 1.9 to 14. In contrast to organic ion-exchangers, inorganic ion-exchangers are not synthesized via complex multi-step
organic synthesis. <strong>The</strong>refore, inorganic ion-exchangers are substantially more cost-effective when compared to organic ionexchangers
as well as CST.
5) PLANS AND THE BASIC TECHNICAL DECISIONS ON SNF REMOVAL FROM ANDREEVA BAY - 16170
Nekhozhin Mikhil, FSUE FCNRS (Russia)
Plans and the basic technical decisions on SNF removal from Andreeva Bay Smirnov V. P, Eshcherkin A.V., Borovitsky S.?.
(<strong>The</strong> Russian Federation, FSUE «FCNRS»)
SESSION 27 - WASTE MINIMIZATION, AVOIDANCE AND RECYCLING
1) A MODEL FOR A NATIONAL LOW LEVEL WASTE PROGRAM - 16372
James Blankenhorn, URS - Washington Division (USA)
A national program for the management of low level waste is essential to the success of environmental clean-up, decontamination
and decommissioning, current operations and future missions. <strong>The</strong> value of a national program is recognized through procedural
consistency and a shared set ofresources. A national program requires a clear waste definition and an understanding of waste
characteristics matched against available and proposed disposal options. A national program requires the development and implementation
of standards and procedures for implementing the waste hierarchy, with a specific emphasis on waste avoidance, minimization
and recycling. It requires a common set of objectives for waste characterization based on the disposal facility’s waste
acceptance criteria, regulatory and license requirements and performance assessments. Finally, a national waste certification program
is required to ensure compliance.
To facilitate and enhance the national program, a centralized generator services organization, tasked with providing technical
services to the generators on behalf of the national program, is necessary. <strong>The</strong>se subject matter experts are the interface between
the generating sites and the disposal facility(s). <strong>The</strong>y provide an invaluable service to the generating organizations through their
involvement in waste planning prior to waste generation and through championing implementation of the waste hierarchy. Through
their interface, national treatment and transportation services are optimized and new business opportunities are identified.
2) CEAS CONTAMINATED LEAD RECYCLING ROUTES - 16011
Marc Butez, Frédéric Hornung, CEA (France)
A route of recycling and valuation of contaminated lead has been in service in the CEA (French Energy Atomic Commission)
since May 2003.
<strong>The</strong> opening of this route required 3 years of instruction of file preparation with the nuclear safety authorities (French regulator)
plus a public inquiry.
Since July 2005 this route has been opened to all the operators of the French nuclear power (CEA, AREVA and EDF).
<strong>The</strong> authorized maximum quantity is 400 tons a year. <strong>The</strong> contaminated lead coming from nuclear installations is decontaminated
at first by fusion in a furnace of the equipment decontamination workshop (ADM) located on the nuclear site of the CEA
MARCOULE.
Lead pieces allowed into the furnace have to have a dose rate lower than 0,3 mGy / hour. At the end of the process the lead
ingots of a mass included between 400 and 500 kg have to have an α and ß activity lower than 1 Bq / g
<strong>The</strong>se ingots are then transformed into biological shieldings for the nuclear industry by an industrial company located in Marseille.
Since the starting of this route about 1280 tons of lead were decontaminated in the ADM and more than 600 tons were valued
and recycled at the various operator’s of nuclear powers CEA and AREVA which corresponds to approximately one hundred of tons
a year for a potential of 400 tons / year.
Having starte essentially with some lead from the CEA facilities of the Marcoule site, the route began to receive lead from the
other sites of the CEA and AREVA NC in 2008.
3) WASAN: A METHODOLOGY FOR ANALYSING WASTE MINIMISATION - 16347
Neil Blundell, Nuclear Installations Inspectorate (UK); Duncan Shaw, Aston Business School (UK)
This paper presents a new methodology called Waste And Source-matter ANalyses (WASAN) which helps a group to analyse
waste-production and build actions to minimise avoidable waste. Designed for Licencees of nuclear facilities as Health and Safety
Executive (HSE) Guidance on what constitutes good practice, WASAN uses lessons from Systems Thinking, Waste Management
Hierarchy, Hazard Operability (HAZOP) Studies, As Low As Reasonably Practicable (ALARP), simulation modelling and sensitivity
analysis. <strong>The</strong>se lessons are used to support groups when developing plans to reduce avoidable waste production. We report
on the development of WASAN and its use in three workshops.
This paper reports progress on the development of waste management guidance for the HSE and does not currently represent
its final regulatory view.
Keywords: Waste Minimisation; Nuclear Industry; Radioactive Waste
4) DELIVERING STEP CHANGE IMPROVEMENTS TO UK LOW LEVEL WASTE STRATEGY - 16188
Jason Dean, National Nuclear Laboratory (UK); David Rossiter, Low Level Waste Repository (UK)
<strong>The</strong> UK Nuclear Industry continues to produce significant quantities of Low Level Waste (LLW) as decommissioning projects
generating waste become more prevalent. Current infrastructure and projected increasing waste volumes will deliver a volumetric
shortfall of storage capacity in the near future. Recently established as a stand alone site licence company, the Low Level Waste
Repository (LLWR) near Drigg, in West Cumbria (formerly operated and owned by British Nuclear Group) is tasked with managing
the safe treatment and disposal of LLW in the UK, on behalf of the Nuclear Decommissioning Authority (NDA).
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Session 27-28 Abstracts
5) BPEO/BPM IN RECYCLING OF LOW LEVEL WASTE METAL IN THE UK - 16210
Joe Robinson, Kevin Dodd, Maria Lindberg, Simon Dickson; Mike McMullen, Studsvik (UK)
Best Practicable Environmental Option (BPEO) and Best Practicable Means (BPM) are concepts well established in the nuclear
industry to help guide and inform waste management decision making. <strong>The</strong> recycling of contaminated metal waste in the UK is not
well established, with the majority of waste disposed of at the low level waste repository at Drigg.
This paper presents an overview of the Strategic BPEO study completed by Studsvik examining the options for low level metal
waste management and a subsequent BPM study completed in support of a proposed metals recycling service. <strong>The</strong> environmental
benefits of recycling metals overseas is further examined through the application of lifecycle analysis to the metals recycling
process.
<strong>The</strong> methodologies used for both studies are discussed and the findings of these studies presented. <strong>The</strong>se indicate that recycling
contaminated metal is the preferred option, using overseas facilities until UK facilities are available. <strong>The</strong> BPM for metals
recycling is discussed in detail and indicates that a tool box for processing metal waste is required to ensure BPM is applied on a
case by case basis. This is supported by effective management of waste transport and waste acceptance criteria. Whilst the transport
of contaminated metal overseas for treatment adds to the environmental burden of metals recycling, this when compared with
the production of virgin metal, is shown to remain beneficial.
<strong>The</strong> results of the Studsvik studies demonstrate the benefits of recycling metals, the options available for such a service and
challenges that remain.
6) EXTERNAL DISPOSAL OF 4 STEAM GENERATORS OUT OF THE DECOMMISSIONING
OF THE NUCLEAR POWER PLANT STADE (KKS) - 16045
Martin Beverungen, GNS Gesellschaft für Nuklear-Service mbH (Germany)
This paper describes the procedure for the qualification of large components (Steam Generators) as an IP-2 package, the ship
transport abroad to Sweden and the external treatment of this components to disburden the Nuclear Power Plant from this task, to
assure an accelerated the deconstruction phase and to minimize the amount of waste.
7) FACTORS INFLUENCING THE PERFORMANCE AND LIFETIME OF FIBROUS
GLASS AND METAL MEDIA HEPA FILTERS - 16285
Charles Waggoner, Michael Parsons, Mississippi State University (USA)
High efficiency particulate air (HEPA) filters are used in a variety of nuclear applications as final air treatment units. <strong>The</strong> design
of air filtration systems in nuclear facilities that will function well requires a significant amount of knowledge about the challenge
conditions that these filters will be exposed to. Additionally, risk assessments conducted as a review of these systems need also to
be based on knowledge of filter challenge parameters during upset conditions that may be used as design basis conditions.
This paper presents a summary of findings of factors that influence the performance lifetime of conventional fibrous glass
media HEPA filters. <strong>The</strong>se factors include aerosol challenge (particle size distributions and mass concentrations), media velocities,
wetting conditions, and changes in gas density. <strong>The</strong>se data are correlated to design considerations for new systems and to process
upset conditions used in risk assessments, particularly those involving fires. Data from filter testing activities are also compared to
filter loading models and to literature information regarding aerosol emission rates from combustion of various materials.
Additional data are provided relating the performance of metal media HEPA filters under conditions that exceed maximum
ranges for fibrous glass filters. <strong>The</strong>se discussions focus on selection factors between these two categories of filter units.
8) INTERNATIONAL RADIOACTIVE METALS RECOVERY, TRANS-FRONTIER
SHIPMENT AND PROCESSING FOR BENEFICIAL REUSE - 16303
Al Johnson, Magnox South (UK)
<strong>The</strong> recycling of Low Level Waste (LLW) contaminated metals resulting from UK decommissioning activities present a number
of technical, political and project management issues. Moreover, the recovery and management of metals that exhibit higher
levels of surface radioactive contamination, encroaching on Intermediate Level Waste (ILW) criteria, represent additional challenges
to both consignors and processors alike. Beneficial re-use is being developed as an alternative means to more conventional
radioactive metals decontamination for clearance and recycling routes in the UK.
This presentation provides an update to a multi-year, multi-site Magnox decommissioning project involving approximately
2000 radioactively contaminated metal pond skips. To date, more than half of these pond skips have been removed, prepared, packaged
and shipped for processing and beneficial reuse in the United States. EnergySolutions and its partners have undertaken metal
melting projects for customers in both North America and Europe, supplying products for beneficial re-usein the nuclear industry
(as opposed to general recycling) to minimize the potential and perceived risk to the public and to maximise the benefit to the
nuclear industry.
SESSION 28 - REPOSITORY PROGRAMS: SITE SELECTION & CHARACTERIZATION,
URL, ENG. & GEOLOGICAL BARRIERS
1) GLOBAL DEVELOPMENTS IN MULTINATIONAL INITIATIVES AT THE BACK END
OF THE NUCLEAR FUEL CYCLE -16294
Charles McCombie, Neil A. Chapman, Arius Association (Switzerland); Tom Isaacs, LLNL/Stanford University (USA)
Interest in expanding nuclear power globally continues to grow and various studies are underway to examine all issues associated
with much expanded nuclear programmes. <strong>The</strong> most open questions today are related to the security and non-proliferation
implications and to the disposal of radioactive wastes. <strong>The</strong> security and proliferation concerns have been almost entirely focussed
on enrichment technology at the front-end of the nuclear fuel cycle and on reprocessing. Although these are the highest risk areas,
it is also important that the potential security problems associated with waste management (in particular with the storage and dis-
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Abstracts Session 28
posal of spent fuel and radioactive wastes) are not neglected. Furthermore, the costs of national geological repositories imply that,
for new or small nuclear programmes, such facilities can be implemented only in the far future, if at all. <strong>The</strong> international community
should continue to strengthen its efforts to highlight the risks and to facilitate solutions that reduce the threats of nuclear materials
being distributed widely across the globe.
In practice, this challenge has been taken up by a number of organisations that are developing initiatives that can alleviate the
potential global security and proliferation problems by promoting multinational approaches to the fuel cycle. This paper addresses
those initiatives that are concerned with the storage and final disposal of radioactive wastes and spent nuclear fuel.
2) US EPAS EXPERIENCES IMPLEMENTING ENVIRONMENTAL SAFETY STANDARDS
AT THE WASTE ISOLATION PILOT PLANT - 16103
Tom Peake, Chuck Byrum, Mike Eagle, Ed Feltcorn, Shankar Ghose,
Rajani Joglekar, US Environmental Protection Agency (USA)
<strong>The</strong> U.S. Environmental Protection Agency (EPA or the Agency) developed environmental standards for the disposal of
defense-related transuranic wastes for the U.S. Department of Energys (DOE or the Department) Waste Isolation Pilot Plant
(WIPP). EPA implements these standards for WIPP, which has been in operation for over ten years. <strong>The</strong> general environmental standards
are set forth in the Agencys 40 Environmental Radiation Protection Standards for the Management and Disposal of Spent
Nuclear Fuel, High-Level and Transuranic Radioactive Wastes. <strong>The</strong>se standards are implemented by site-specific compliance criteria.
<strong>The</strong> WIPP Land Withdrawal Act requires DOE to submit a re-certification application every five years after the initial receipt
of waste. DOE submitted the latest WIPP re-certification application in March 2009. For re-certification, DOE must identify
changes that have occurred over the previous five years and analyze their impact on the potential long-term performance of the
repository. Once EPA determines that the re-certification application is complete, the Agency has six months to review the application
and make a final decision. During this review, EPA solicits and incorporates public comment where appropriate. During the
first re-certification in 2004, several stakeholder groups brought up issues (e.g., karst) that were addressed in the original certification.
EPA has received comments again raising some of these same issues for the 2009 re-certification.
In addition, DOE must submit proposed changes to the WIPP repository to EPA for review and approval. This paper describes
selected issues of concern to WIPP and highlights interactions between EPA as the regulatory authority and DOE as the implementing
organization. In general EPAs experience points out the importance of communication, documentation and the regulators
responsibility in determining how much is enough.
3) REPOSITORY SITE CHARACTERIZATION — COMPARING INTERNATIONAL EXPERIENCE - 16082
Martin Goldsworthy, Golder Associates (Germany); Till Popp, IfG Institut für Gebirgsmechanik GmbH (Germany); Knut
Seidel, GGL Geophysik und Geotechnik Leipzig GmbH (Germany); Johannes Bruns, Golder Associates (Germany)
An important part of the work described here was a study of existing international experience in investigating deep geological
repository sites. <strong>The</strong> objective of this study was to derive a basis for planning the content and extent of investigations which might
be carried out in Germany in the future. Such investigations would be required in the course of a site selection process for a repository
for HLW (high level radioactive waste). For this purpose information on suitable sites was gathered, mainly from literature
sources. Suitable in this context meant two things. Firstly, the investigated site should be in rock similar to four being considered
in Germany (salt, clay, crystalline and other hard rock under a clay cover). Secondly, the investigations carried out could reasonably
be considered as being intended to lead to the use of the site as a repository.
<strong>The</strong> investigation processes were presented, analysed and compared. <strong>The</strong> comparison was based on the quality and the intensity
of the methods employed to obtain the information necessary for deciding between candidate repository sites in terms of safety
and the feasibility of construction. In the final stage of the work the analysis and presentation method developed for the international
sites was applied to the investigations already carried out at three German sites (Gorleben — a prospective HLW repository,
Morsleben — an existing but now not operational repository for radioactive waste and Konrad — a repository currently under construction).
<strong>The</strong> reported investigatory work was compared with the ideal investigations developed on the basis of the existing international
experience.
4) AMENDMENTS TO THE U.S. ENVIRONMENTAL PROTECTION AGENCYS PUBLIC HEALTH AND
ENVIRONMENTAL RADIATION PROTECTION STANDARDS FOR YUCCA MOUNTAIN, NEVADA - 16156
Ray L. Clark, Ken Czyscinski, Reid J. Rosnick, Daniel Schultheisz, US Environmental Protection Agency (USA)
<strong>The</strong> Energy Policy Act of 1992 (EnPA) directed the U.S. Environmental Protection Agency (EPA or the Agency) to establish
standards to protect public health and safety from releases of radioactive material stored or disposed in the proposed repository for
spent nuclear fuel and high-level waste at Yucca Mountain, Nevada. <strong>The</strong> EnPA also required EPA to contract with the National
Academy of Sciences (NAS) for a study on reasonable standards for disposal, and for the standards to be based upon and consistent
with the findings and recommendations of the NAS.
In June 2001, the Agency issued standards addressing both storage and disposal at the Yucca Mountain facility. <strong>The</strong> disposal
standards included three components: an individual-protection standard, a human intrusion standard, and ground-water protection
standards. A number of parties, including the State of Nevada, the Natural Resources Defense Council, and the Nuclear Energy
Institute, filed petitions for review of the standards. In July 2004, a Federal Court upheld EPA on all counts except for the compliance
period associated with the individual-protection standard, which the Agency had limited to 10,000 years for a number of technical
and policy reasons. However, NAS had recommended that the standard be set for the time of peak risk, within the limits
imposed by the long-term stability of the geologic environment, which NAS estimated at 1 million years. EPAs standards required
that the Department of Energy (DOE) project doses to the time of peak dose, but did not apply a compliance standard to these
longer-term projections. <strong>The</strong> Court ruled that EPAs 10,000-year compliance period was inconsistent with the NAS recommendation.
This aspect of the rule was vacated and remanded to the Agency for revision.
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Session 28 Abstracts
EPA proposed amendments to its standards in August 2005, and provided 90 days for public comment. <strong>The</strong> Agency held meetings
and hearings in Nevada and Washington, D.C. during the comment period. <strong>The</strong> final standards were issued in October 2008,
along with a separate document containing responses to all public comments.
This paper will describe and discuss the amendments to EPAs standards, including the compliance period, the individual-protection
standard, the statistical method to measure compliance, the method by which doses are calculated, and specifications regarding
features, events, and processes.
5) EXPERIENCE WITH TECHNICAL ADVISORY GROUPS IN THE
JAPANESE HLW DISPOSAL PROGRAMME - 16290
Hiroyuki Tsuchi, Kazumi Kitayama, Akira Deguchi, Yoshiaki Takahashi,
Nuclear Waste Management Organization of Japan (Japan); Toshiaki Ohe, Tokai University (Japan):
Charles McCombie, Arius Association (Switzerland); Ian McKinley, McKinley Consulting (Switzerland)
<strong>The</strong> Japanese HLW implementing organisation, NUMO, was established 10 years ago and, over this period, has been very successful
in developing a high international profile and a reputation for innovative approaches to solving technical issues. To some
extent this reflected the solid basis of technical expertise that had already been built up over the previous 20 years, but the need for
innovation also resulted from the special boundary conditions required by the decision to adopt a volunteering approach to repository
siting. It was recognised that a call for volunteers had to be supported by solid documentation of the site selection approach
particularly the exclusion criteria which are very important in a seismically active country like Japan. Additionally, NUMO as an
organisation had to be recognised as technically credible, particularly with regard to tailoring the design of disposal facilities and
the associated safety case to the specific conditions found in volunteer sites. To facilitate achieving both these ambitious goals,
NUMO set up both domestic and international technical advisory committees that drew together the experience needed.
Although there was some overlap, the domestic advisory committee (DTAC) with its sub-committees was mainly charged with
developing a technical consensus on the supporting science and technology associated with site selection and characterisation,
repository design and long-term safety assessment. As such, the total number of members was large and they were drawn predominantly
from academia, professional societies and R&D organisations. <strong>The</strong> international committee (ITAC) focused more on putting
Japanese work into a wider context and on drawing on experience both positive and negative - from national programmes that
had advanced further. Hence ITAC members were originally selected on an ad personam basis because they had comprehensive
knowledge of national waste management programmes. Although it was not the original primary focus, the involvement of ITAC
members with NUMO grew with time so that most also actively participated in particular NUMO projects.
6) CURRENT STATUS OF PHASE II INVESTIGATION, MIZUNAMI
UNDERGROUND RESEARCH LABORATORY (MIU) PROJECT - 16262
Tadahiko Tsuruta, Masahiro Uchida, Katsuhiro Hama, Hiroya Matsui, Shinji Takeuchi, Kenji Amano, Ryuji Takeuchi,
Hiromitsu Saegusa, Toshiyuki Matsuoka, and Takashi Mizuno, Japan Atomic Energy Agency (Japan)
<strong>The</strong> Mizunami Underground Research Laboratory (MIU) Project, a comprehensive research project investigating the deep
underground environmental in crystalline rock, is being conducted by Japan Atomic Energy Agency at Mizunami City, Central
Japan. <strong>The</strong> MIU Project is being carried out in three overlapping phases: Surface-based Investigation (Phase I), Construction (Phase
II), and Operation (Phase III), with a total duration of 20 years. <strong>The</strong> overall project goals of the MIU Project from Phase I through
to Phase III are: 1) to establish techniques for investigation, analysis and assessment of the deep geological environment, and 2) to
develop a range of engineering for deep underground application. Phase I was completed in March 2004, and Phase II investigations
associated with the construction of the underground facilities are currently underway.
Phase II investigation goals are to evaluate geological, hydrogeological, hydrogechemical and rock mechanical models developed
in Phase I and to assess changes in the deep geological environment caused by the construction of underground facilities. Geological
mapping, borehole investigations for geological, hydrogelogical, hydrogeochemical and rock mechanical studies are being
carried out in shafts and research galleries in order to evaluate the models. Long-term monitoring of changes in groundwater chemistry
and pressure associated with the construction of the underground facilities continue in and around the MIU site, using existing
borehole and monitoring systems.
This report summarizes the current status of MIU Project on results of the Phase II investigations to date.
7) APPROACHES FOR MODELLING TRANSIENT UNSATURATED-SATURATED
GROUNDWATER FLOW DURING AND AFTER CONSTRUCTION - 16242
Matt White, Galson Sciences Limited (UK); Jordi Guimera,AMPHOS XXI Consulting S.L (Spain);
Hiroshi Kosaka, Takuya Ohyama, Japan Atomic Energy Agency (Japan);
Peter Robinson,Quintessa Limited (UK) Hiromitsu Saegusa, Japan Atomic Energy Agency (Japan)
Construction of underground research laboratories and geological disposal facilities has a significant transient impact on
groundwater flow, leading to a drawdown in the water table and groundwater pressures, and groundwater inflow into shafts, access
ways and tunnels accompanied by desaturation of the surrounding rock. Modelling the impact of underground facilities on groundwater
flow is important throughout the construction and operation of the facilities, e.g. estimating grouting and water treatment
facility requirements during construction, and estimating the rate of resaturation of the engineered barrier system and the establishment
of steady-state groundwater flow after backfilling and closure.
Estimating the impact of these effects requires modeling of transient groundwater flow under unsaturated conditions at large
scales, and over long timescales. This is a significant challenge for groundwater flow modelling, in particular because of the nonlinearity
in groundwater flow equations, which can have a marked effect on suitable timesteps for transient calculations. In addition,
numerical grids need to be developed at appropriate scales for capturing the transition between saturated and unsaturated
regions of the sub-surface, and to represent the features of complex hydrogeological structures such as heterogeneous fractured
rock.
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Abstracts Session 28-29
<strong>The</strong> Japan Atomic Energy Agency (JAEA) has been developing modelling techniques to overcome these problems as part of
the Mizunami Underground Research Laboratory (MIU) Project in the Tono area of Gifu Prefecture, Japan. An integrated geological
and hydrogeological modelling, and visualisation system referred to as GEOMASS has been developed, which allows for transient
unsaturated groundwater flow modelling in the presence of dynamic underground excavation models. <strong>The</strong> flow simulator in
GEOMASS, FracAffinity, allows for such modelling by the application of sophisticated gridding techniques, allowing for modification
of hydraulic conductivity in key zones, and by suitable modification of water retention models (the relationship between saturation
and pressure, and saturation and hydraulic conductivity).
8) INTEGRATED MODEL OF KOREAN SPENT FUEL AND HIGH LEVEL WASTE DISPOSAL OPTIONS - 16091
Yongsoo Hwang, KAERI (Korea); Ian Miller, GoldSim Technology Group (USA)
This paper describes an integrated model developed by the Korean Atomic Energy Research Institute (KAERI) to simulate
options for disposal of spent nuclear fuel (SNF) and reprocessing products in South Korea. A companion paper (Hwang and Miller,
2009) describes a systems-level model of Korean options for spent nuclear fuel (SNF) management in the 21st century.
<strong>The</strong> model addresses alternative design concepts for disposal of SNF of different types (CANDU, PWR), high level waste, and
fission products arising from a variety of alternative fuel cycle back ends. It uses the GoldSim software to simulate the engineered
system, near-field and far-field geosphere, and biosphere, resulting in long-term dose predictions for a variety of receptor groups.
<strong>The</strong> model’s results allow direct comparison of alternative repository design concepts, and identification of key parameter
uncertainties and contributors to receptor doses.
SESSION 29 - MODELING APPROACHES FOR HLW, SNF, AND TRU WASTE DISPOSITION
1) DEVELOPMENT OF THE ENVI SIMULATOR TO ESTIMATE KOREAN SNF FLOW AND ITS COST - 16060
Yongsoo Hwang, KAERI, Daejeon,Korea (Republic), Ian Miller, GoldSim Technology Group, Issaquah, WA,United States
This paper describes an integrated model developed by the Korean Atomic Energy Research Institute (KAERI) to simulate
options for managing spent nuclear fuel (SNF) in South Korea. A companion paper (Hwang and Miller, 2009) describes a performance
assessment model to address the long-term safety of alternative geological disposal options for different waste streams.
<strong>The</strong> model addresses alternative concepts for storage, transportation, and processing of SNF of different types (CANDU,
PWR), leading up to permanent disposal in geological repositories. It uses the GoldSim software to simulate the logistics of the
associated activities, including the associated capital and operating costs.
<strong>The</strong> model’s results allow direct comparison of alternative waste management concepts, and predict the sizes and timings of
different facilities required. Future versions of the model will also address the uncertainties associated with the different system
components in order to provide risk-based assessments.
2) INTEGRATION OF THE H2 INHIBITION EFFECT OF UO2 MATRIX
DISSOLUTION INTO RADIOLYTIC MODELS - 16239
Yongsoo Hwang, KAERI (Korea); Ian Miller, GoldSim Technology Group (USA)
Different models describing the dissolution mechanism of spent nuclear fuel under repository conditions have been developed
in the last years. One of the most evolved ones is the Matrix Alteration Model (MAM), which is an Alteration/Dissolution source
term model based on the oxidative dissolution of spent fuel. Oxidant and reducing species can be naturally or radiolytically-generated.
<strong>The</strong> experimentally-observed inhibition of matrix dissolution by H2 , was integrated into MAM by considering that H2 is able
to consum the oxidant species responsible for UO2 dissolution, e.g. H2O2 . As a consequence, MAM predicts lower H2O2 concentrations
for systems containing larger amounts of dissolved H2.
On the other hand, radiolysis experiments carried out by Pastina and coworkers have shown that under specific conditions, i.e.
high linear energy transfer (LET) radiation and absence of solid phase, dissolved H2 has a negligible effect on the H2O2 concentration,
thus suggesting that the H2 inhibition effect catalyzed by the matrix surface has not been properly implemented in MAM.
Modelling exercises performed in this work confirms such point and reveals the necessity of considering H2-activation when modelling
this king of systems. In addition, it has been demonstrated that, for high LET radiation, a clear dependence exists between
the extent of the H2 activation and the integral LET of the radiation. <strong>The</strong> integration of the function describing such dependence
allows to improve the implementation of the H2 inhibition effect in MAM.
3) SEPARATION OF LANTHANOID PHOSHATES FROM THE SPENT ELECTROLYTE
OF PYROPROCESSING - 16265
Ippei Amamoto, Hirohide Kofuji, Munetaka Myochin, Japan Atomic Energy Agency (Japan); Tatsuya Tsuzuki, Central
Glass Co.Ltd (Japan); Yasushi Takasaki, Akita University (Japan);Tetsuji Yano, Tokyo Institute of Technology (Japan);
Takayuki Terai, <strong>The</strong> University of Tokyo (Japan)
This study is carried out to make the pyroprocessing hold a competitive advantage from the viewpoint of environmental load
reduction and economical improvement. As one of the measures is to reduce the volume of the high-level radioactive waste, the
phosphate conversion method is applied for removal of fission products from the melt as spent electrolyte in this paper. Though the
removing target elements in the medium are alkali metals, alkaline earth metals and lanthanoid elements, only lanthanoid elements
and lithium form the insoluble phosphates by reaction with Li3PO4 or K3PO4 .
<strong>The</strong>refore, as the first step, the precipitation experiment was carried out to observe the behaviours of elements which form the
insoluble precipitates as double salts other than simple salts. <strong>The</strong>n the filtration was experimented to remove lanthanoid precipitates
in the spent electrolyte using Fe2O3-P2O5 glass system as a filtlation medium which is compatible material with the glassification.
<strong>The</strong> result of separation of lanthanoid precipitates by filtration was effective and attained almost 100%.
93

Session 29-30 Abstracts
4) IMPLEMENTATION OF A GEOLOGICAL DISPOSAL FACILITY (GDF) IN THE UK BY THE NDA RWMD:
COUPLED MODELLING OF GAS GENERATION AND MULTI-PHASE FLOW BETWEEN
THE CO-LOCATED ILW AND HLW/SF COMPONENTS OF A GDF - 16307
Alex Bond, George Towler, Alan Paulley, Quintessa Limited (UK); Simon Norris, NDA RWMD (UK)
In June 2008 the UK government published a White Paper as part of the Managing Radioactive Waste Safety(MRWS) programme
to provide a framework for managing higher activity radioactive wastes in the long-term through geological disposal. <strong>The</strong>
White Paper identifies that there are benefits to disposing all of the UKs higher activity wastes (Low and Intermediate Level Waste
(LLW and ILW), High Level Waste (HLW), Spent Fuel (SF), Uranium (U) and Plutonium (Pu)) at the same site, and this is currently
the preferred option. It also notes that research will be required to support the detailed design and safety assessment in relation
to any potentially detrimental interactions between the different modules.
Different disposal system designs and associated Engineered Barrier Systems (EBS) will be required for these different waste
types, i.e. ILW/LLW and HLW/SF. If declared as waste U would be disposed as ILW and Pu as HLW/SF. <strong>The</strong> Geological Disposal
Facility (GDF) would therefore comprise two co-located modules (respectively for ILW/LLW and HLW/SF).
A study has recently been undertaken by NDA RWMD to identify the key <strong>The</strong>rmo-Hydro-Mechanical-Chemical (THMC)
interactions which might occur during both the operational and post-closure phases in order to assess the potential implications of
co-location in a range of host rocks. This paper presents supporting modelling work used to help understand the potential interactions
between the modules. A multi-phase flow and coupled gas generation model was used to help investigate the potential groundwater
and gas fluxes between the modules, in particular considering the operational phase and resaturation behaviour of the different
modules. <strong>The</strong>se early phases are important because gas generation rates and hydraulic gradients will be at their maximum, and
the pressure gradients associated with GDF operations will, at least initially, dominate over the background hydraulic gradient.
SESSION 30 - SPENT FUEL, HLW, AND TRU WASTE MANAGEMENT - CROSSCUTTING ISSUES
1) THE U.S. DEPARTMENT OF ENERGY OFFICE OF ENVIRONMENTAL MANAGEMENT(DOE-EM)
INTERNATIONAL COOPERATIVE PROGRAM - EFFORTS BEING CONDUCTED UNDER THE
STATEMENT OF INTENT BETWEEN DOE-EM AND U.K. NUCLEAR DECOMMISSIONING
AUTHORITY (NDA) AND FUTURE INTERNATIONAL ACTIVITIES – 16338
Steven L. Krahn, Kurt D. Gerdes, Ana M. Han, U.S.Department of Energy (USA); James Marra, SRNL (USA)
<strong>The</strong> DOE-EM Office of Engineering and Technology is responsible for implementing EM’s international cooperative program.
<strong>The</strong> Office of Engineering and Technology’s international efforts are aimed at supporting EM’s mission of risk reduction and accelerated
cleanup of the environmental legacy of the nation's nuclear weapons program and government-sponsored nuclear energy
research. To do this, EM pursues collaborations with government organizations, educational institutions, and private industry to
identify and develop technologies that can address the site cleanup needs of DOE.
A Statement of Intent was signed between DOE-EM and the NDA to work cooperatively on areas of mutual interest. Under
this umbrella, discussions were held with NDA representatives to identify potential areas for collaboration. Information and technical
exchanges were identified as near-term actions to help meet the objectives of the Statement of Intent. <strong>The</strong> organizations have
shared planning and technology need documents. Comparisons of these documents were used to identify target areas for future collaborative
work. Information exchanges have already occurred in several areas. Information and experience in conducting technology
readiness assessments has been shared between the organizations. This included completed technology readiness assessment
reports, as well as technology maturation plans. A near-term goal is to have members from each organization participate or observe
the readiness assessment process of the other organization. Information exchanges have also occurred in two other areas. Several
videoconferences have been conducted between vitrification experts supporting the work of both DOE-EM and the NDA. In these
videoconferences current research and technology focus areas have been discussed. Technical documents have also been exchanged
in areas of mutual interest. Similar videoconferences have been held with experts involved in the area of nuclear materials science
and engineering. Specific discussions have focused on materials challenges associated with environmental management and
cleanup.
2) IMPLEMENTATION OF A GEOLOGICAL DISPOSAL FACILITY (GDF) IN THE UK BY THE NDA RWMD:
THE POTENTIAL FOR INTERACTION BETWEEN THE CO-LOCATED ILW/LLW AND HLW/SF
COMPONENTS OF A GDF - 16306
George Towler, Quintessa Limited (UK); Tim Hicks, Galson Sciences Ltd (UK);
Sarah Watson, Quintessa Limited (UK); Simon Norris, NDA RWMD (UK)
In June 2008 the UK government published a White Paper as part of the Managing Radioactive Waste Safety (MRWS) programme
to provide a framework for managing higher activity radioactive wastes in the long-term through geological disposal. <strong>The</strong>
White Paper identifies that there are benefits to disposing all of the UKs higher activity wastes (Low and Intermediate Level Waste
(LLW and ILW), High Level Waste (HLW), Spent Fuel (SF), Uranium (U) and Plutonium (Pu)) at the same site, and this is currently
the preferred option. It also notes that research will be required to support the detailed design and safety assessment in relation
to any potentially detrimental interactions between the different modules.
Different disposal system designs and associated Engineered Barrier Systems (EBS) will be required for these different waste
types, i.e. ILW/LLW and HLW/SF. If declared as waste U would be disposed as ILW and Pu as HLW/SF. <strong>The</strong> Geological Disposal
Facility (GDF) would therefore comprise two co-located modules (respectively for ILW/LLW and HLW/SF). This paper presents
an overview of a study undertaken to assess the implications of co-location by identifying the key <strong>The</strong>rmo-Hydro-Mechanical-Chemical
(THMC) interactions that might occur during both the operational and post-closure phases, and their consequences
for GDF design, performance and safety.
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Abstracts Session 30-31
<strong>The</strong> MRWS programme is currently seeking expressions of interest from communities to host a GDF. <strong>The</strong>refore, the study was
required to consider a wide range of potential GDF host rocks and consistent, conceptual disposal system designs. Two example
disposal concepts (i.e. combinations of host rock, GDF design including wasteform and layout, etc.) were carried forward for
detailed assessment and a third for qualitative analysis.
Dimensional and 1D analyses were used to identify the key interactions, and 3D models were used to investigate selected interactions
in more detail. <strong>The</strong> results of this study show that it is possible for ILW/LLW and HLW/SF modules to be collocated without
compromising key safety functions of different barrier components, and this reflects international precedents, e.g. the Andra
and Nagra repository designs. <strong>The</strong>re are two key technical issues that need to be managed in designing the geometry of the co-located
GDF: (i) the heat flux from the HLW/SF module interacting with the ILW/LLW module, and (ii) the potential for development
of an alkaline plume from the ILW/LLW module interacting with the HLW/SF module; particularly within fractured host rocks.
3) THE ROLE OF THE SAVANNAH RIVER NATIONAL LABORATORY AS THE DOE ENVIRONMENTAL
MANAGEMENT CORPORATE LABORATORY - 16175
Samit Bhattacharyya, John Marra, Jeff Griffin, William Wilmarth, Savannah River National Laboratory (USA)
<strong>The</strong> presentation describes the critical role of the Savannah River National Laboratory (SRNL) in effecting progress in the
monumental multi-decade mission of the Department of Energys Office of Environmental Management (DOE-EM). As the EM
Corporate Laboratory, SRNL uses the full technical and management capabilities and resources of the nations principal applied
technology laboratory to assist EM in the identification, development, and deployment of effective technological solutions to EM
clean-up problems as well as to support emergent EM initiatives.
<strong>The</strong> mission of DOE-EM is to safeguard the health of people and the environment by cleaning up nuclear waste, nuclear materials,
contaminated groundwater & soil, and facilities—involving two million acres of land located in thirty-five states—from fifty
years of nuclear weapons research and production. EM also seeks to find ways to reduce and reuse nuclear byproducts generated
now and in the future.
A rigorous EM management system is in place today and institutionalized for continuity across changes in political will. As
the EM Corporate Laboratory, SRNL provides the corporate infrastructure to facilitate dynamic communication and collaboration
across a virtual technical support community of national laboratories, universities, federal agencies, and international entities to
achieve EMs goals effectively and efficiently.
One of SRNLs critical efforts is to assist the DOE-EM technology development and deployment program and guide the implementation
of the DOE-EM Engineering & Technology Roadmap, which was developed with SRNL support and formally issued in
March 2008. <strong>The</strong> EM Roadmap identifies five program areas that are central to site cleanup, the technical risks and uncertainties
associated with each program area, and strategic initiatives to address each uncertainty. A Multi-Year Program Plan accompanies
the Roadmap.
4)EVOLUTION OF THE QUALITY ASSURANCE PROGRAM FOR TRU WASTE REPOSITORY OPERATIONS,
WASTE CHARACTERIZATION AND TRANSPORTATION AT THE WASTE ISOLATION PILOT PLANT - 16152
Ava L. Holland, Department of Energy (USA)
This paper explores the evolution of quality assurance as a concept and as a management system over the life of the Waste Isolation
Pilot Plant, the first operational geologic repository for nuclear waste. Activities and approaches that have led to successes
and failures and the resulting lessons learned will be explored from the perspective of Quality Assurance Organization management.
Quality assurance has been an integral element of the processes involved in siting, design, construction, and operation of the
Waste Isolation Pilot Plant. Over time, QA Program scope and basic concepts have grown and evolved due to influences related to
project stage and political needs. Initially, the WIPP QA program was focused on development of computer models and collection
and use of data for repository performance assessment. This work was performed using QA Program controls provided by the
National Laboratories involved in model development and data collection and analysis. Initial repository site construction used a
QA Program to provide the needed controls for design, welding, procurement, inspection, and other basic construction quality
needs. Multiple QA Programs were involved across the early WIPP activities, with no single programmatic blueprint for integration
across the broad range of activities.
During WIPPs pre-operational phase, the need for a single, integrated QA Program became apparent. <strong>The</strong> first program
description was scoped for waste characterization activities that were defined in 40 CFR 191 and 194, and basic repository construction
and operational needs. As the pre-operational phase progressed, additional needs for QA Program coverage were identified,
particularly in the area of transportation.
SESSION 31 - ER SITE CHARACTERIZATION AND MONITORING - PART 1 OF 2
1) A PRACTICAL APPROACH TO CHARACTERISE AND ASSESS A SITE DRAINAGE
SYSTEM IN SUPPORT OF SITE RESTORATION - 16008
Angela Bartlett, UKAEA Harwell (UK); Gavin Coppins, UKAEA (UK); Peter Burgess, Nuvia (UK)
Part of the nuclear site restoration and delicensing process involves the characterisation and assessment of below-ground
drainage systems. Site restoration is currently underway at Harwell in Oxfordshire where there is a complex drainage system that
has developed over more than 70 years. Drainage decommissioning involves visual inspections, jet-washing and radiological surveys
prior to final grouting. Prior to decommissioning, the structural and radiological condition of the network was unknown and
now requires characterisation and assessment against defined clean-up criteria before the land can be released for future use.
This paper outlines the application of an innovative Geographic Information System (GIS) and data management methodology
to assess the structural and radiological condition of the drainage network at Harwell. <strong>The</strong> approach demonstrates the importance
of efficient data collection and storage, implemented using UKAEAs IMAGES land quality data management system. It also
details several GIS techniques that can be utilised to accurately position below-ground surveys and record pipe material and diameter
for surveyed drain sections.
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Session 31 Abstracts
<strong>The</strong> aim of the monitoring process is to identify any activity which exceeds the delicensing criteria set by the Nuclear Installations
Inspectorate (NII). <strong>The</strong> relevant criteria are the residual activity and the risk to a future site occupier. <strong>The</strong> maximum missable
activity for each pipe class was determined by considering instrumentation characteristics and natural background radiation
levels. <strong>The</strong> equipment used (a caesium iodide scintillation probe connected to a ratemeter), was limited by the small diameter of
some drains. <strong>The</strong> hypothesis chosen was that residual activity was most likely to lie along the base of the pipe, given that the drains
generally ran with only a limited depth. <strong>The</strong> response was measured for Cs-137 gamma radiation and then used to calculate the net
count rate for a variety of pipe configurations. Variability of the data was investigated in relation to static probe response and variations
in counts per second along a pipe length. Analysis of the data using GIS showed clear spatial patterns, indicating systematic
variability within each pipe material and diameter class.
2) BENEFITS OF LRGS IN ASSESSMENT AND REMEDIATION OF ALPHA CONTAMINATION - 16023
Martha McBarron, Aker Solutions (UK); Jim Cassidy, Fathoms Ltd (UK),
Louise Hutton, Low Level Waste Respository (UK)
<strong>The</strong> legacy of alpha contamination in an exterior disusedstorage area at the Low Level Waste Repository (LLWR) presented
difficult challenges with regard to assessment and remediation. <strong>The</strong> area was heavily overgrown, with degraded remnant surfaces
and debris from past demolition activities. <strong>The</strong> use of conventional field instruments and/or an extensive intrusive sampling programme
were precluded as being impractical, the latter prohibitively costly and not expeditious. This paper describes the identification
of a cost-effective alternative for the initial site assessment and the role of LRGS in the subsequent remediation work. It
includes:
1 identification and selection of a field instrumentation/system for investigating the site.
2 details of the TERRIERTM system, incorporating the SAM935 Low Resolution Gamma Spectrometer (LRGS) with the
capability of real time identification of nuclides.
3 use of the TERRIERTM for a non-intrusive survey of the site, with rapid transformation of field data into informative plots
useful for remediation planning.
4 use of the TERRIERTM during remediation work, including assay of arisings.
5 benefits and limitations of using LRGS to support remediation of alpha contamination.
6 application of the instrumentation/system to other radiological investigations.
3) SAFE MANAGEMENT OF RADIOACTIVE MATERIALS FOUND IN PUBLIC LOCATIONS – 16032
Andrew Lewcock, Safeguard <strong>International</strong> Solutions Ltd. (UK);
Colette Grundy, Catherine Shaw, Environment Agency (UK)
In January 2006 the Environment Agency for England and Wales requested assistance in preparing a project to plan, collect
and safely dispose of radium painted aluminium aircraft hatches, discovered in 3 separate business premises in the UK. <strong>The</strong>se
World-War Two aircraft hatches had been marked with radium “luminous” paint, to guide crew in the dark to the escape exits if
they needed to bale out. <strong>The</strong> hatches had been stored since the early 1960s in one location, with some of the inventory being moved
two other locations in 2003/2004. <strong>The</strong> North West Region of the Environment Agency appointed a consortium of Enviros, Safeguard
<strong>International</strong> and Aurora Health Physics to undertake the work, and they funded it from the sealed sources disposal budget.
<strong>The</strong> paper will set out how the project was complicated by an assortment of “real world” problems; preliminary estimates of
both the activity per hatch and the number of hatches established the potential for a significant quantity of radium to be disposed
of safely. <strong>The</strong> total number of hatches was not known for sure at the start of the work. Access to retrieve the majority of the frames
was hazardous due to the poor structural condition of the building roof. Other difficulties included constrained access under a railway
line, and bird-related biohazards. <strong>The</strong> sites involved in the collections were not intended to house radioactive materials, so
physical security was another important issue. Some of the hatches were known to be in poor condition, with a very high probability
of radium contamination being spread to the surrounding areas. <strong>The</strong> hatches had to be removed from the sites before the full
extent of contamination of other materials could be established.
4) AN INTEGRATED SYSTEM FOR CONDUCTING RADIOLOGICAL SURVEYS
OF CONTAMINATED SITES - 16312
Charles Waggoner, Donna Rogers, Jay McCown, Mississippi State University (USA)
This paper describes an integrated detection system has been developed to conduct radiological surveys of sites suspected of
contamination of materials such as depleted uranium. This system utilizes cerium activated lanthanum bromide and thallium activated
sodium iodide gamma detectors and can be easily adapted to include units for detecting neutrons. <strong>The</strong> detection system
includes software controlling the collection of radiological spectra and GPS data. Two different platforms are described for conducting
surveys, a modified zero turn radius (ZTR) mower and a three-wheeled cart that is manually pushed.
<strong>The</strong> detection system software controlling data collection has components that facilitate completing a gridless survey on user
specified spacings. Another package confirms that all data quality activities (calibrations, etc.) are conducted prior to beginning the
survey and also reviews data to identify areas that have been missed of for which data quality falls below user designated parameters.
Advanced digital signal processing algorithms are used to enhance the interpretation of spectra for conducting background subtractions
and for mapping. Data from radiation detection and GPS antennae are merged and made compatible with mapping using
Geosoft Oasis montaj software.
A summary of system performance during field-testing is included in the paper. This includes survey rate, detection limits, duty
cycle, supporting ancillary equipment/material, and manpower requirements. <strong>The</strong> rate of false positives and false negatives is discussed
with the benefits of surveys conducted using synergetic detection systems such as electromagnetic induction imaging
96

Abstracts Session 31
5) INTERDIGITATED ELECTRODE ARRAY BASED SENSORS FOR MONITORING OF CAESIUM - 16123
Ian D Nickson, John Tyndall Institute for Nuclear Research (UK); Colin Boxall, Lancaster University (UK);
G. Garnham,National Nuclear Laboratory (UK); Simon. N Port, DSTL (UK)
<strong>The</strong> requirement for on-line and in-situ monitoring of analytes in process and effluent streams and in ground waters has become
increasingly more important in recent years. We therefore describe the development of the transduction element for a fully automated
online instrument for the detection of caesium. <strong>The</strong> sensor layer for this instrument employs an Ion Selective Conductimetric
microsensor (ISCOM) as the detector. This is based upon a plasticized polymeric membrane incorporating a selective ionophore,
overlaying two interdigitated microelectrode arrays. A direct relationship has been observed between the bulk conductance (as
determined by the microelectrodes) of the ionophore loaded membrane and the concentration of the primary ions in solution.
Caesium selective ISCOMs were prepared using a ion selective membrane containing the commercially available ionophore
Calix[6]arene-hexaacetic acid hexaethyl ester, polyvinylchloride (PVC) and plasticiser Nitrophenylether (NPOE). Methods of ion
selective membrane deposition have been investigated in order to obtain a maximal response. <strong>The</strong> relative levels of membrane components
have also been varied in order to further enhance the ISCOM reponse. We also present preliminary data concerning the
caesium selectivity with respect to a range of possible interferents, including rubidium.
6) CONE PENENTRATION TESTING OF RADIOLOGICALLY CONTAMINATED BURIAL TRENCHES - 16086
Gareth Walker, Matt Lennard, Jeremy Lightfoot, Golder Associates (UK); Nick Jefferies, Serco Assurance (UK)
Golder Associates (UK) Ltd, in partnership with Serco Assurance (Serco), undertook targeted cone penetration testing (CPT)
of a series of six parallel on-site burial trenches on a nuclear licensed site in the UK. <strong>The</strong> form and concentration of radioactive and
chemical material within the trenches is unknown. CPT was used to confirm the location of the bund walls and to characterise the
material within the trenches <strong>The</strong> CPT technique involves hydraulically pushing rods fitted with specialist characterisation “cones”
into the ground. CPT generates no solid or liquid waste, and allowed rapid investigation of the trenches and bunds while ensuring
exposure of radiation and contamination to workers was kept to a minimum, or removed in entirety. As a result of the unknown
nature of radiological contamination within the trenches and the potential of introducing contamination into the inside of the CPT
truck, a purpose-built extraction rig was constructed to withdraw the CPT equipment from the ground. Extraction of the equipment
assumed airborne radioactive contamination was a potential hazard. <strong>The</strong> CPT locations selected for the investigation were based on
non-intrusive geophysical survey work and a radiation survey, which identified the approximate location of the trenches, anomalies
within the material (e.g. metallic objects), and radiation hotspots. <strong>The</strong> results of the geophysical surveys were overlaid with the
original as-built drawings of the trenches. During the investigation the following investigation cones were deployed: •
Resistance/friction cone, which determines geology through measurement of the friction on the sleeve of the cone and resistance
on the tip of the cone; this was used to investigate the geology of the bunds. • Total gamma cone, which was used to obtain total
gamma radiation results (in counts per second); • Groundwater sampler (BAT SamplerTM), which was used to obtain a water sample
from beneath the trenches; • Video cone, which was used to obtain a visual recording of the material within the trenches; and •
Conductivity cone, which was used to investigate the presence of and depth to bodies of water below ground level (e.g. perched
water, regional groundwater).
7) THE ADVANCED PEGASUS OVERLAND RADIATION DETECTION SYSTEM - 16321
Jeffrey Lively, Alejandro Lopez, Michael Marcial, MACTEC (USA); Mark Liddiard, Joe Toole, WorleyParsons (UK)
A variety of technical challenges are presented when one wishes to make radiological measurements over large areas of land.
Aside from the physical challenges posed by the land surface itself, the radiological composition, the physical properties, and the
nature of deposition of the contaminant often pose formidable scientific challenges. No one system or approach can be ideally suited
to every circumstance. One of the most formidable circumstances one could face in open land radiological surveys is the challenge
of locating discrete particle contaminants that may be widely distributed over large land areas. <strong>The</strong> measurement challenge
is akin to “hunting for the needle in a haystack.” While overland surveys have been performed by various means for many years,
the methods employed are often ineffective or utterly inadequate to address the confident detection of “super heterogeneous” contaminants
at reasonable activity thresholds.
At least three areas of inter-tidal contamination by particulate radioactive contamination have been identified in the UK. <strong>The</strong>se
cover substantial areas which can only be effectively monitored by vehicle based systems and are subject to rapid changes caused
by weather and tidal cycles. Of these contaminated sites, the most well known is the beaches that lie in proximity to the Dounreay
plant in northern Scotland. Other beach environments adjacent to the Sellafield plant and a former Royal Air Force (RAF) airfield
in eastern Scotland are also impacted with discrete radioactive particle contamination.
8) THE EFFECT OF HIGH-SCATTER SHIELDING GEOMETRIES IN VALIDATING
THE DOSE INFERRED BY N-VISAGE(TM) - 16130
Jamie Adams, Lancaster University (UK); Matthew Mellor, React Engineering Ltd. (UK);
Malcolm Joyce, Lancaster University (UK)
<strong>The</strong> aim of this paper is to further validate the physical capability of N-Visage” under more challenging shielding geometries,
when the number of mean free paths is greater than one. N-Visage” is a recently established technique developed at REACT Engineering
Ltd. <strong>The</strong> software locates radionuclide sources and contours radiation magnitude. <strong>The</strong> N-Visage” software uses a geometric
computer model combined with measured spectra. <strong>The</strong> software is able to estimate source locations through shielding materials
by using mass attenuation coefficients to calculate the number of unscattered gamma photons arriving at the detector, and buildup
factors to estimate scatter contribution to dose rate. <strong>The</strong> experiments described in this paper were carried out in a high-scatter
environment using cobalt-60 and caesium-137 sources, these two sources are the primary sources of radiological contamination
found in the nuclear industry. It is hoped that this will further assist in the identification, characterisation and removal of buried
radiologically contaminated waste.
97

Session 32 Abstracts
SESSION 32 - LOCAL PARTICIPATION AND DECISION-MAKING PROCESSES, BEHAVIOR AND POLITICS
1) THREATS AND BENEFITS UPDATED INFORMATION ON LOCAL OPINIONS REGARDING THE SPENT
NUCLEAR FUEL REPOSITORY IN FINLAND - 16128
Matti Kojo, University of Tampere (Finland); Mika Kari, Tapio Litmanen, University Jyväskylä (Finland)
<strong>The</strong> aim of the paper is to provide updated information on local opinion regarding the siting of a spent nuclear fuel repository
in Finland. <strong>The</strong> main question is how the residents of the municipality perceive the threats and benefits of the repository. In accordance
with the Decision in Principle by the Council of State passed in 2000, the Olkiluoto area in Municipality of Eurajoki was
chosen as the location for the repository to accommodate spent nuclear fuel produced in Finland.
Updated information on local opinions is needed as the siting process is approaching the next phase, the application for a construction
license by 2012. <strong>The</strong> nuclear waste management company Posiva, owned by the utilities Teollisuuden Voima and Fortum
Power and Heat, has also applied for a new Decision in Principle (DiP) for expansion of the repository.
<strong>The</strong> data provided in this paper is based on a survey carried out in June 2008. <strong>The</strong> respondents were selected from the residents
of the municipality of Eurajoki and the neighbouring municipalities using stratified random sampling (N=3000). <strong>The</strong> response
rate of the survey was 20% (N=606).
<strong>The</strong> paper is part of a joint research project between the University of Jyväskylä and the University of Tampere. <strong>The</strong> research
project Follow-up research regarding socio-economic effects and communication of final disposal facility of spent nuclear fuel in
Eurajoki and its neighbouring municipalitiesis funded by the Finnish Research Programme on Nuclear Waste Management
(KYT2010).
2) APPLYING BEST PRACTICAL ENVIRONMENTAL OPTIONEERING (BPEO) TO A COMPLEX CLEAN UP
PROGRAMME; A PONDS & SILOS CASE STUDY - 16154
Simon Candy, Sellafield Ltd. (UK)
<strong>The</strong> use of Best Practical Environmental Optioneering (BPEO) has long been part of informed decision making within the
Nuclear Industry. However, BPEO has typically been applied to specific and discrete objectives, for example the selection of a technology
to treat a particular nuclear waste stream. While this has sometimes been extended to cover a number of objectives, no one
had applied BPEO to a programme of the size and complexity of that associated with Legacy Ponds & Silos at Sellafield. <strong>The</strong> programme,
spanning more than 30 years, includes a range of different objectives covering ongoing management, recovery, conditioning,
storage and ultimately disposal of nuclear wastes. This range of activities is applied across a number of facilities containing
multiple, significant waste streams. This paper explains how BPEO was applied to the Legacy Ponds & Silos programme and discussed
some of the learning resulting from that exercise.
3) STAKEHOLDER PARTICIPATION FOR THE LEGACY PONDS AND LEGACY SILOS (LP&LS) FACILITY AT
SELLAFIELD, CUMBRIA. UK: THE NATURE AND EFFECTIVENESS OF THE DIALOGUE - 16030
John Whitton, UK National Nuclear Laboratory (UK)
<strong>The</strong> Legacy Ponds and Silos (LP&S) facilities are part of the UK nuclear legacy located at the Sellafield Site, Cumbria. <strong>The</strong>re
are four individual facilities containing nuclear wastes that have accumulated over a period of approximately 50 years. Waste
retrieval and conditioning, in preparation for decommissioning, is currently being carried out by the site operator. LP&S have
recently proposed a re-engagement with stakeholders following the initial engagement in December 2005. This paper reviews this
earlier engagement in terms of the nature of dialogue that was carried out when compared against definitions of deliberation provided
in the literature. <strong>The</strong> aim of this paper is to provide those planning future engagement with a better understanding of how the
nature of dialogue can vary and uses participation and deliberation as indicators of effective engagement.
A concern of those working towards a programme of effective stakeholder participation in 2005 was how to ensure genuine
dialogue and stakeholder representation in such a strictly controlled and regulated environment with a technical complexity that
challenges technical specialist and layperson alike. LP&S recognised that effective dialogue with stakeholders on the available
technical options and their associated societal impacts would form a significant part of this process if options were to prove resilient.
However, the challenge presented to LP&S was how to engage stakeholders on a variety of projects, whilst ensuring the output
could be used by the projects as part of their technical decision making.
4) EXPERIENCE IN CHOICES FOR DECOMMISSIONING THE DOUNREAY SITE - 16183
Fred Catlow, Fred Catlow, Independent Nuclear Consultant (UK)
<strong>The</strong> paper describes the public participation from the viewpoint of a stakeholder and member of the public.
<strong>The</strong> dialogue between various members of the Dounreay Stakeholders Committee vary widely and do not always seem to represent
the views of the wider public. Whilst great care has been taken to select various options for the ultimate condition of the
Dounreay site and these have been discussed at great length and the preferred option selected by consensus, there still appears to
be some conflict within the local community.
It is my belief (and others) that if the local population had to vote on the options for the the future of the Dounreay nuclear site
the outcome would be vastly different from that of the Stakeholders Committee.
Whilst the politicians have been elected by the people, they represent a distinctly anti-nuclear view (even to the extent of
decommissioning) whereas the majority of the local population would prefer to see a continuation of nuclear activity on the Dounreay
site.
<strong>The</strong> problem is not only with local politicians but at bational level in Scotland itself where the Scottish National Party has
formed a coalition with the Green Party on condition all nuclear activities are phsed out.
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Abstracts Session 33
SESSION 33 - DIALOGUE TECHNIQUES: DIALOGUE VERSUS CONSULTATION,
COMM. OF RISK, EDU., USE OF WEB TECH.NOLOGY
1) TRAINING ACTIVITIES AND PERSPECTIVES IN THE RADIOACTIVE WASTE
MANAGEMENT AREA OF MOSCOW SIA “RADON” - 16131
Olga Batyukhnova, Scientific and Industrial Association “Radon” (Russia);
Arthur Arustamov, Natalia Arustamova, Sergey Dmitriev, SUE SIA “Radon” (Russia);
Michael Ojovan, University of Sheffield (UK); Zoran Drace, <strong>International</strong> Atomic Energy Agency (Austria)
<strong>The</strong> education service for specialists dealing with radioactive waste was established in Russia (former USSR) in 1983 and was
based on the capabilities of two organisations: Moscow Scientific and Industrial Association «Radon» (SIA Radon) and
Lomonosovs Moscow State University. <strong>The</strong>se two organizations are able jointly to offer training programs in the science fundamentals,
applied research and in practical operational areas of the all pre-disposal activities of the radioactive waste management
(RWM).
Since 1997 this system was upgraded to the international level and now acts as the <strong>International</strong> Education Training Centre
(IETC) at SIA Radonunder the guidance of the IAEA. During last 12 years more than 350 specialists from 33 European and Asian
countries enhanced their knowledge and skills in RWM.
<strong>The</strong> IAEA supported many specialized regional training courses and workshops, fellowships, on-the-job training, and scientific
visits which are additional means to assure development of personnel capabilities.
Efficiency of training was analysed at IETC using the structural adaptation of educational process as well as factors, which
have influence on education quality. In addition social-psychological aspects were also taken into account in assessing the overall
efficiency. <strong>The</strong> analysis of the effect of individual factors and the efficiency of education activity were carried out based on appraisal
results and post-course questioning of attendees.
2) EVALUATING LILRW REPOSITORY IMPACTS DUE TO TECHNOLOGIC STIGMA – 16229
Mojca Golobic, Alenka Cof, University of Ljubljana (Slovenia); Marko Polic, University of Ljubljana (Slovenia)
Scientific argumentation is proving increasingly inadequate to legitimize a site for LILRW repository. It is being increasingly
replaced by negotiating compensations for so called technologic stigma. However, the amount of fair compensation and the entitled
community are difficult to determine due to the lack of reliable estimations of extent and the level of stigmatization impact.
This paper presents a study, which tried to estimate these impacts for two alternative sites in Slovenia. We assumed that the impacts
occur due to the technologic stigma affecting the behavior of consumers in real estate, food and tourism markets. <strong>The</strong> level and the
reach of the impact were estimated by questioning real estate appraisers and agents, consumers in food markets and tourists. <strong>The</strong>
results have confirmed that some impacts can be expected but their level can only be estimated approximately and in an aggregated
form. We could also confirm that the behavior of the actors is not consistent with their attitudes. We conclude that the results are
not a very reliable base for determining individual revenues. However, they indicate slightly different level of the impact in each
community, related to distance from the repository as well as the border between municipalities. As such, the results can be used
in deciding between the alternative sites. Based on our research we could also suggest that individual compensations may be unfair
and that investments in reducing technologic stigma with emphasizing positive image of the community would achieve higher benefit
for the community.
3) RADIOACTIVE WASTE: SHOW TIME? - 16309
Hans Codee, COVRA N.V., Ewoud Verhoef, COVRA (Netherlands)
Time will render radioactive waste harmless. How can we manage the time radioactive substances remain harmful? Just wait
and see or marking time is not an option.
We need to isolate the waste from our living environment and control it as long as necessary. For the situation in the Netherlands,
it is obvious that a period of long term storage is needed. Both the small volume of waste and the limited financial possibilities
are determining factors. Time is needed to let the volume of waste grow and to let the money, needed for disposal, grow in a
capital growth fund.
An organisation such as COVRA the radioactive waste organisation in the Netherlands - can only function when it has good,
open and transparent relationship with the public and particularly with the local population. If we tell people that we safely store
radioactive waste for 100 years, they often ask: That long?How can we explain the long-term aspect of radioactive waste management
in a way people can relate to? In this paper, an overview is given of the activities of COVRA on the communication of radioactive
waste management.
4) EXPERIENCES OF TEACHING DECOMMISSIONING - 16179
Fred Catlow, Independent Nuclear Consultant (UK)
<strong>The</strong> paper describes the experience gained in teaching decommissioning in the Highlands of Scotland.
Initially when I was asked to teach the subject of decommissioning to students sitting for a BSc degree in Electrical or Mechanical
Engineering with Decommissioning Studies, I was taken aback as I had not previously taught degree students and there was
no precedent since there was no previous material or examples to build on. It was just as difficult for the students since whilst some
had progressed from completing HND studies, the majority were employed on the Dounreay site and were mature students with
families who were availing themselves of the opportunity for career advancement (CPD). Some of the students were from the
UKAEA and its contractors whilst others were from Rolls-Royce working at Vulcan, the Royal Navys establishment for testing
nuclear reactors for submarines. A number of the students had not been in a formal learning environment for many years.
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Session 34 Abstracts
<strong>The</strong> College which had originally been funded by the UKAEA and the nuclear industry in the 1950s was anxious to break into
the new field of Decommissioning and were keen to promote these courses in order to support the work progressing on site. Many
families in Thurso, and in Caithness, have a long tradition of working in the nuclear industry and it was thought at the time that
expertise in nuclear decommissioning could be developed and indeed exported elsewhere. In addition the courses being promoted
by the College would attract students from other parts so that a centre of excellence could be established. In parallel with formal
teaching, online courses were also developed to extend the reach of the College.
<strong>The</strong> material was developed as a mixture of power point presentations and formal notes and was obtained from existing literature
web searches and interactive discussions with people in the industry as well as case studies obtained from actual situations.
Assignments were set and examination papers prepared which were validated by internal and external assessors.
<strong>The</strong> first course was started in 2004 (believed to be unique at that time) and attracted eight students. Subsequent courses have
been promoted as well as a BEng (Hons) course which also included a course on Safety and Reliability.
SESSION 34 - POSTER SESSION - LOW/INTERMEDIATE LEVEL WASTE
A) THE ROCK CREEP EVALUATION IN THE ANALYSIS SYSTEM FOR THE LONG-TERM
BEHAVIOR OF TRU WASTE DISPOSAL SYSTEM - 16110
Shintaro Ohno, Seiji Morikawa, Kajima Corporation (Japan); Morihiro Mihara, Japan Atomic Energy Agency (Japan)
MACBECE (Mechanical Analysis system considering Chemical transitions of BEntonite-based and CEment-based materials)
is an analysis system to evaluate the long term mechanical behavior in the TRU (TRans Uranium) waste disposal system. TRU
wastes are low level radioactive wastes that include long-lived nuclides. MACBECE is the system to calculate mechanical and
chemical behavior in the near field including engineered barriers in the TRU waste disposal system, and subsequently to evaluate
the hydraulic property in various components. MACBECE can evaluate the mechanical/hydraulic alterations of two types of barrier
materials, cement-based and bentonite-based materials. <strong>The</strong>se materials, in the long-term, may be altered internally by chemical
reaction. To evaluate the long-term mechanical behavior due to the chemical transitions, the nonlinear elastic model for the
cement-based materials and the elasto-viscoplastic model for the bentonite-based materials were applied, based on the data from
various laboratory tests. Also, proposed models based on the data from permeability tests were applied to evaluate the alteration of
hydraulic conductivity.
So as to realize the high reliable evaluation, the variable-compliance-type constitutive model proposed by Okubo (1992) was
newly adopted for the rock creep evaluation in MACBECE. This creep model can express analytically nonlinear visco-elastic
behavior and the over-peak-strength state behavior. This paper focuses on the adoptability of rock creep model in MACBECE.
Applicability of the rock creep model is verified by conducting the numerical simulations with the long-term mechanical interaction
between the TRU waste disposal system and the host rock.
B) COMPARISON OF ACTINIDES SEPARATION BY COPRECIPITATION AND ACTINIDE
CHROMATOGRAPHIC RESIN (DIPEX®) FOR GROSS ALPHA DETERMINATION - 16249
Esperanza Lara, Marina Rodriguez, CIEMAT (Spain)
<strong>The</strong> determination of gross alpha in wastes which have alpha, beta and gamma emitters is very important from a regulatory
point of view. <strong>The</strong> level of alpha radioactivity to storage is very limited in a low and medium level radioactive location for safety
reasons, so it is necessary to measure it with high precision.
In order to quantify the radioactive concentration of alpha emitters it is necessary to perform an adequate radiochemical separation
before its measuring.
In this paper has been studied and compared the resuls obtained by two separation methods: one by coprecipitation using
BaSO4 , Fe(OH) 3 and/or CaC2O4 as precipitant agents and the other one by extraction cromatogaraphy using Actinide Resin
(Dipex®). <strong>The</strong> separation procedures have been applied to spent ion exchange resins from Spanish Nuclear Power Plants.
Once the sample was dissolved by acid digestion in a closed vessel microwave equipment, and the radionuclides of interest
were isolated of the rest by the techniques before mentioned, the gross alpha was measrured by Liquid Scintillation Counting, using
the α/β discrimination if it was necessary (when the separation was not completed), since this technique is today one of the most
atractive and sensitive for measuring radioactivity because LS spectrometry can detect practically all types of radiation with high
efficiency.
C) NOVEL ANTIMONYSILICATE MATERIAL QUASAR-N FOR THE REMOVAL OF
RADIONUCLIDES FROM ACIDIC DECONTAMINATION LIQUIDS - 16157
Risto Harjula, Airi Paajanen, University of Helsinki (Finland)
Novel antimony silicate material, commercially available from PQ Corporation (previously Ineos Silicas) is highly selective
for the removal of several key radionuclides (Co-60, Sr-90, Cs-137, Pu-236 and Am-241) from acidic and neutral nuclear waste
effluents. <strong>The</strong> paper will summarise most the key results that have been obtained in the previous studies of the material. In addition,
new test results on the removal Co-60, Sr-90, Cs-137 and Am-241 from acid media are reported. Static batch experiments and
column experiments show that Am can be removed efficiently from nitric and oxalic acid, indicating that Quasar is suitable e.g. for
the purification of acidic decontamination solutions.
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Abstracts Session 34
D) FURTHER DEVELOPMENT OF IODINE IMMOBILIZATION TECHNIQUE BY
LOW TEMPERATURE VITRIFICATION WITH BIPBO2I - 16268
Atsushi Mukunoki, Tamotsu Chiba, JGC Corporation (Japan);Yasuhiro Suzuki, JGC Corporation (Japan);
Kenji Yamaguchi,Tomofumi Sakuragi, Radioactive Waste Management Funding and Research Center (Japan);
Tokuro Nanba, Okayama University (Japan)
<strong>The</strong> authors describe progress in the development of low temperature vitrification with BiPbO2I (BPI) as a promising immobilization
technique by which Iodine-129 is recovered by BiPbO2NO3 to form BPI, and then solidified into a lead-boron-zinc
glass matrix (PbO-B2O3-ZnO) using a low temperature vitrification process. <strong>The</strong> microscopic structure of BPI glass was analyzed
by various analytical techniques, such as XRD (X-ray diffraction), NMR (nuclear magnetic resonance analysis), and XPS
(X-ray photoelectron spectroscopy), using several types of glass samples. <strong>The</strong> results obtained provide structural information on
key elements in BPI glass and can be applied for modeling the structure of the BPI glass, simulated by molecular dynamics. <strong>The</strong>
previous work suggested that the leaching behavior of iodine from BPI glass depended upon the chemical conditions of the solution.
Further leaching tests using solutions under varying conditions were carried out in order to predict mechanisms of iodine
leaching. Normalized elemental mass loss values of iodine in simulated seawater and bentonite pore water are almost the same as
those of boron, showing that iodine dissolves congruently with BPI glass, whereas iodine dissolves incongruently in Ca(OH) 2
solutions of pH 9 and 11. To demonstrate the feasibility of the BPI vitrification process, recovery tests of iodine from spent
iodine filters were conducted and a prototype melting furnace was developed for scale-up tests of glass sample. It was found that
more than 95% of iodine can be recovered from the spent iodine filter and that the prototype furnace can produce approximately
0.5 liters of homogeneous glass.
E) IMPROVEMENT OF INSTITUTIONAL RADIOACTIVE WASTE MANAGEMENT VIA THE
IMPLEMENTATION OF THE ENVIRONMENTAL MANAGEMENT SYSTEM - 16094
Marija Fabjan, Agency for Radwaste Management (Slovenia);Metka Kralj, Bojan Hertl, ARAO - Agency for Radwaste
Management (Slovenia); Jože Rojc, RŽV - Mine Žirovski Zvrh (Slovenia)
Managing of institutional radioactive waste in Slovenia is one of the main processes in the management system of Agency for
Radwaste Management (ARAO). <strong>The</strong> management system integrates the quality management system ISO 9001 and the environmental
management system that was certified according to the standard ISO 14001:2004 in October 2007.
<strong>The</strong> certificate represents a permanent commitment of ARAO to improve the environmental management system of ARAO and
to implement environmental planning. Environmental planning includes and maintains environmental objectives and targets in all
ARAO’s activities, especially in managing the institutional radioactive waste which can have potential environmental impacts and
is considered as a risky activity from the public site of view. We defined a general ARAO’s register of environmental aspects with
seven main groups of aspects. Each aspect was evaluated according to its impacts with the help of multiple criteria and only the
aspects evaluated as significant are dealt with in further environmental planning.
Environmental planning was implemented in the process of managing of institutional radioactive waste. Our methodology for
evaluating the significance of environmental aspects showed three significant aspects. Appropriate environmental objectives and
targets were defined for these aspects in a way that they were measurable, if applicable, consistent with the ARAO?s environmental
policy. It was assured that they provided adequate environmental protection measures and protection of human health, compliance
with national legal requirements and international directives dealing with radioactive waste management and that the production
of radioactive waste was minimised. <strong>The</strong> environmental planning is carried out annually, and each year we are looking for
opportunities to minimise potential environmental impacts of our service.
F) THE KNOO RESEARCH CONSORTIUM: WORK PACKAGE 3 AN INTEGRATED APPROACH
TO WASTE IMMOBILISATION AND MANAGEMENT - 16375
Simon Biggs, Michael Fairweather, James Young, University of Leeds (UK); Robin Grimes, Imperial College London
(UK); Neil Milestone, University of Sheffield (UK): Francis Livens, <strong>The</strong> University of Machester (UK)
<strong>The</strong> Keeping the Nuclear Option Open (KNOO) research consortium is a four-year initiative addressing the challenges related
to increasing the safety, reliability and sustainability of nuclear power in the UK. Through collaboration between key industrial
and governmental stakeholders and international partners, KNOO has been established to maintain and develop skills relevant to
nuclear power generation. Funded by a research grant of £6.1M from the Towards a Sustainable Energy Economy Programme of
the UK Research Councils, it represents the single largest university-based nuclear research programme in the UK for more than
30 years. <strong>The</strong> programme is led by Imperial College London, in collaboration with the universities of Manchester, Sheffield, Leeds,
Bristol, Cardiff and the Open University. <strong>The</strong>se universities are working with BNFL, who contributed a further £0.5M, with other
stakeholders including AWE, British Energy, the Department for Environment, Food and Rural Affairs, the Environment Agency,
the Health and Safety Executive, Doosan Babcock, the Ministry of Defence, Nirex, AMEC NNC, Rolls-Royce PLC and the UK
Atomic Energy Authority.
Work Package 3 of this consortium, led by the University of Leeds, concerns An Integrated Approach to Waste Immobilisation
and Management, and involves Imperial College London, and the Universities of Manchester and Sheffield. <strong>The</strong> aims of this work
package are: to study the re-mobilisation, transport, solid-liquid separation and immobilisation of particulate wastes; to develop predictive
models for particle behaviour based on atomic scale, thermodynamic and process scale simulations; to develop a fundamental
understanding of selective adsorption of nuclides onto filter systems and their immobilisation; and to consider mechanisms of
nuclide leaving and transport.
<strong>The</strong> paper will describe work underway in the key areas of multi-scale modelling (using atomic scale, thermodynamic and
process scale models), the engineering properties of waste (linking microscopic and macroscopic behaviour, and transport and rheology),
and waste reactivity (considering waste hosts and wasteforms, generation IV wastes, and waste interactions).
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Session 34 Abstracts
G) HYDRAULIC BEHAVIOUR OF NUCLEAR WASTE FLOWS - 16376
Simon Biggs, Michael Fairweather, David Harbottle, Bo Lin,James Young, Jeff Peakall, University of Leeds (UK)
A great deal of existing nuclear waste is stored as a solid-liquid slurry, and the effective transportation of solid-liquid systems
is an essential element in the successful implementation of almost all waste treatment strategies involving particulate wastes within
the nuclear industry. A detailed knowledge of turbulent, particle-laden liquid flow behaviour is therefore obviously important.
However, systematic studies of solid-liquid flows by experimental investigation are still limited for pipe flows, contrary to the significant
amount of work available for channel flows. Research work is therefore required to understand the effects physical parameters,
such as particle shape, size and size distribution, and solids concentration, on the properties of solid-liquid systems, particularly
in horizontal pipe flows where particles may settle out of the flow and form solid beds which can potentially lead to pipe blockages.
<strong>The</strong> presence of particles in a turbulent pipe flow also modifies the characteristics of the flow, thereby changing its ability to
maintain particles in suspension
Work is currently underway to examine pipe flows over a Reynolds number range of 5,200-10,040, with varying levels of
solids concentration within the flow. Measurements of the flow and particle characteristics are being gathered using particle image
velocimetry (PIV) and, for high solids concentrations, ultrasound Doppler velocity profiling (UDVP) techniques. Work to date has
demonstrated that the intensity of turbulence with such flows can be significantly affected by the presence of solid particles, with
small particles generally attenuating turbulence levels, while large particles often augment turbulence levels from the pipe centreline
to the near-wall region. In addition, the coagulation of particles into larger agglomerates is also of importance, with data
demonstrating that whilst turbulence levels are influenced and augmented by such agglomerates at low Reynolds numbers, high
turbulence levels at high Reynolds numbers can destroy the agglomerates and reduce their effect on the carrier fluid.
H) ENGINEERING PROPERTIES OF NUCLEAR WASTE SLURRIES - 16378
Simon Biggs, Michael Fairweather, Tim Hunter, Qanita Omokanye, Jeff Peakall, James Young, University of Leeds (UK)
<strong>The</strong> types of particulate systems encountered in legacy nuclear waste slurries are highly complicated, with the aggregation and
flow behaviour being at times very variable. However, deconstructing the complex overall slurry activity to singular particle-particle
interactions can lead to a greater understanding of the mechanisms involved in particle aggregation, and so to predictions of
their settling and flow in nuclear systems. Of particular importance to legacy waste is the role of salts in controlling the attraction
of particles (and so in dictating the rheological properties of the system) as sludges may contain a variety of specific ions and generally
have high ionic conductivity. In this paper, work on the characterisation of particle-particle interactions using a number of
complimentary methods will be described, together with measurements of their influence on the resulting flow and solid bed compression.
<strong>The</strong> methods used to characterise the particle-particle interactions under various salt and pH conditions were firstly, atomic
force microscopy. This device allows quantitative measurement of particle attraction, and so the propensity of particles to aggregate
in different conditions. Particle-particle interactions were also related to zeta-potential measurements, which highlights the
changing surface-charge of particles under various conditions. Most importantly, the individual particle-surface properties were correlated
to the rheological behaviour of suspensions, in particular, the shear and compressional yield stresses, vital parameters in dictating
flow and dewatering performance, respectively. Interestingly, it was found that with certain di- and tri-valent salts there were
specific ion adsorption effects, which altered the expected yield stress relationships and could not be explained by classical valence
theories. Together, these techniques have enabled the characterisation of a range of particulate systems that may be encountered in
legacy wastes, with results pointing to a number of important factors that could help explain the observed variability in industrial
slurry behaviour.
I) RADIOACTIVE WASTE MANAGEMENT IN KENYA - 16366
Anthony Shadrack, Ministry of Health (Kenya)
Many countries have been firmly committed to the peaceful applications of ionizing radiations in medicine, industry, agriculture
and training and research in order to achieve socioeconomic development in diverse sectors. <strong>The</strong> objective of this project is to
highlight the current situation with the storage facilities for the radioactive wastes and disused sealed radioactive sources in Kenya.
In Kenya sealed radioactive sources are used in various socio-economic disciplines such as medicine, industry, research and agriculture.
At the end of their useful lives, these radioactive sources become ionizing radiations waste and can still be dangerous
because they can cause harmful effects to the public and the environment. “Borehole disposal design concept” is used for sitting
up a safe site for storage of radioactive waste for sealed radioactive sources in the country. <strong>The</strong> methodology to be used will involve
using borehole drilling technology that is readily available in the country. <strong>The</strong> design can accommodate disused sources of less than
100mm in length and 16 mm in diameter. It is assumed that the sources are disposed at least 40 m from the ground surface thereby
significantly reducing the probability of the waste being disturbed by human intrusion or other disruptive events and processes.
This document focuses safe management of spent radioactive sources generated from various applications in medicine, agriculture,
training and research and industry. <strong>The</strong> main research facility is situated at the material science branch Ministry of Public Works
(MOPW) which is situated 2 km north of the capital. <strong>The</strong>re are 4 nuclear medicine centers, 3 industrial radiotherapy facilities, 2
gamma irradiator facilities, one linear accelerator, 2 high dose radiation (HDR) Brachytherapy units, 5 industrial radiography units
and several training and research facilities (colleges, universities and secondary schools) in the country. Results are tabled in this
paper to show safe management of radioactive sources in Kenya.
J) THE COMPLEXATION OF TC(IV) WITH GLUCONIC ACID AT HIGH PH - 16381
Sneh Jain, Ricky Hallam, Peter Warwick, Nick Evans, Loughborough University (UK)
In the UK, a technetium containing floc may be disposed of in a high pH, low Eh cementitious repository, whereupon the floc
would degrade by alkaline hydrolysis and/or radiolysis releasing the Tc into the porewater. Its chemistry would then be dominated
by TcO4-, in aerobic waters and the sparingly soluble TcO2(s) in anaerobic. Repository heterogeneity could mean that both Tc(VII)
and Tc(IV) are present simultaneously. If TcO4- migrates into reducing conditions, organic ligands in the waste may complex with
Tc during reduction to form water-soluble complexes. Also possible, is increased Tc solubility when organic ligands react with
102

Abstracts Session 34-36
TcO2(s). For gluconic acid the Tc aqueous concentration starting from TcO4- and reducing the mixture was higher than in systems
with TcO2 as the starting point. This suggests that the pertechnetate was not reduced to TcO2, but an intermediate oxidation state
complex was formed, e.g. Tc(V). <strong>The</strong> conditional stability constant for the Tc(IV)-gluconic acid complex has been determined to
be log = 26.6 ± 0.2.
K) MANAGEMENT OF METAL WASTE WITH HIGH CONCENTRATION OF NATURAL
RADIONUCLIDS, ITS PROBLEMS AND EXPERIENCE - 16222
Alexander B. Gelbutovskiy, JSC “ECOMET-S"(Russia) Peter I.Cheremisin, Alexander V. Troshev, Ecomet-S (Russia)
<strong>The</strong> given work describes the problem and the offered solutions for the NORM contaminated metal waste generated in the oil
& gas and other non-atomic industries. <strong>The</strong> Russian Federation regulatory base, the fundamental metal LLW treatment scheme in
accordance with Sanitary Rules and standards are given. It is shown, that one of the treatment ways is the processing at a specialized
enterprise. Such an only enterprise in Russian Federation is the Joint-Stock Company (JSC) ECOMET-S. Its main activities
are radwaste management, processing and disposal of the metal LLW. <strong>The</strong> operations main goal is to reduce the waste volume to
its minimum before further burial and to return the clean metal to the unrestricted commercial turnover.
<strong>The</strong> worked out technology and the enterprise industrial capacity are represented. JSC ECOMET-Sactivities results and processing
and disposal schedule are given.
L) STUDY OF THE RADIOACTIVE SILT SEDIMENT CEMENTATION TECHNIQUES - 16138
Scientific-Industrial Association Radon (Russia); Elena Zaharova, Vycheslav Ermolaev, IPCE RAS (Russia)
In this paper the following techniques were considered for the silt processing: the cementation of silt without a prior treatment,
cementation of the dried silt product, cementation of the calcined silt product, and the impregnation of the calcined silt with high
penetrating cement grouts.
This paper reports the results of the following studies: the chemical and isotope silt composition, physicochemical silt properties,
properties of the cement grouts and solidified compounds, obtained as a result of various silt processing techniques.
For every processing technique the following cement compound quality index stated in the Russian standard GOST R 51883-
2002 was determined: the mechanical strength, freeze-thaw resistance and leach rate of 137Cs. Effects of variations in the thermal
silt treatment mode, in the water/cement ratio, and in the binder material type have been determined.
Based upon the results of the studies a comparative assessment of the silt cementation techniques has been performed.
M) 5000TH MOSAIK - CASK DELIVERED IN 2007 - A STORY OF SUCCESS - 16216
Olaf Oldiges, GNS Gesellschaft fuer Nuklear (Germany)
Been undertaken to examine the effect of particle size and Reynolds number on particle deposition within the flows, and also
to establish the minimum transport velocity required to re-suspend particles from solid beds. All these findings are of importance
in enhancing our understanding of flows of particles in pipes which in turn is of value in enabling the design of cost effective and
efficient waste treatment processes.
N) CEMENTATION OF PROBLEM LRW USING POROUS CONCRETE - 16139
Andrey Varlakov, Aleksandr Germanov, Aleksandr Barinov,Sergey Dmitriev, Moscow Scientific-Industrial Association
Radon (Russia); Arthur Arustamov, SUE SIA Radon (Russia)
Problem wastes are defined as those wastes which are solidified with difficulty, have poor volumetric efficiencies or produce
an unsatisfactory product, demands much of radiation safety of technological process. <strong>The</strong>se wastes are organic liquid (oil, solvents,
extractants, scintillation cocktail and others), high containing surface-active substances, subacid aqueous saline and high containing
alpha nuclides LRW.
<strong>The</strong> technology consists in as follows. First of all, porous concrete is prepared by a special mixer and placed into a container.
<strong>The</strong> container is the standard drum 100 or 200 l. At the age-hardening of concrete not less than 28 days, when main hydration
processes are finished, problem LRW is pumped into the pore space of the porous concrete matrix through previously positioned
the special feed tube. <strong>The</strong> hardened porous concrete matrix is impregnated with problem liquid radioactive wastes which penetrate
into the pore space. Depending on kind of LRW contents of waste in the final product has made 50-65 % vol. <strong>The</strong> final conditioning
product has meet requirements. LRW is fixed very reliable inside pores of the cement matrix
O) SEPARATION OF LANTHANIDE FISSION PRODUCTS IN A EUTECTIC WASTE SALTS
DELIVERED FROM PYROPROCESSING OF A SPENT OXIDE FUEL BY
USING LAB-SCALE OXIDATIVE PRECIPITATION APPARATUS - 16127
Yung-Zun Cho, Korea Atomic Energy Research Institute (Korea)
Co-precipitation experiments of lanthanides were carried out using this lab-scale apparatus(4kg-salt/batch). As lanthanides, 8
lanthanide elements(Y, La, Ce, Pr, Nd, Sm, Eu and Gd) were used. By reaction with oxygen, these 8 lanthanide chlorides were converted
their oxide(REO2, RE2O3) or oxychloride form. Since these lanthanide oxides or oxychlorides are nearly molten salt insoluble,
they all were precipitated by free settling in the bottom of molten salt bed, where about 7-8 hrs precipitation time was requested.
It was found that in the conditions of 700 ? - 12 hours sparging time and 5 L/min, all the used lanthanide elements showed over
99.5% oxidation efficiency. But in case of 800 ? molten salt temperature only after 7 hours they showed over 99% oxidation efficiency.
103

Session 35-36 Abstracts
SESSION 35 - PANEL: THE UK OBJECTIVES AND STRATEGY FOR
THE MANAGEMENT OF ITS NUCLEAR LEGACY
ABSTRACTS NOT REQUIRED
SESSION 36 - D&D TECHNOLOGIES - PART 1 OF 2
1) OPTIONS FOR THE REMOVAL OF CONTAMINATED CONCRETE FROM THE BORE
OF THE WINDSCALE PILE CHIMNEY - 16083
Colin Campbell, Dr Jeremy Hunt, Sellafield Limited (UK);Stephen Hepworth, Sellafield Ltd (UK)
A legacy of the 1957 Windscale Pile reactor fire is the penetration of radioactive contamination into the internal surface concrete
of the chimney bore. Gamma imaging of Cs-137 has shown that the contamination is widespread throughout the chimney, and
core samples have shown that the contamination has penetrated to depths of around 5-25mm. <strong>The</strong> Pile chimney is 100m tall and
has an internal bore diameter of 15m. It is constructed of a hard concrete comprised of Whinstone aggregate. <strong>The</strong> baseline decommissioning
scheme is to remove approximately 5-25mm of the surface concrete from the entire bore of the chimney.
<strong>The</strong> technology baseline in 2006 was to remove layers of contaminated concrete by mechanical means using shavers or scabblers.
However, risks associated with mechanical technologies that may preclude their use include: the ability of mechanical devices
to remove the hard concrete; clogging of the devices due to wet concrete; and deployment of the delivery systems. This paper discusses
the options under consideration to reduce the risks associated with the removal of the contaminated concrete through application
of alternative techniques.
<strong>The</strong> present baseline technology is high pressure water jetting technique. Demonstrations have shown that this technology can
successfully remove concrete without significant reaction forces. However, an inherent problem with this technology is the production
of secondary liquid effluent waste, which would need to be treated by an appropriate conditioning process. To address the secondary
effluent waste issue, technologies that produce little or no secondary waste have been considered. <strong>The</strong> technologies that
have been considered are laser scabbling, microwave scabbling and nitrogen jet blasting. <strong>The</strong> paper discusses each technique in
turn, highlighting their advantages and disadvantages. <strong>The</strong> results of an in-active laser scabbling and high pressure liquid nitrogen
jetting trial are presented. <strong>The</strong> paper concludes with a discussion of the merits of each technology in support of the future strategy
for concrete removal.
2) DECOMMISSIONG OF ACTIVE EFFLUENT GANTRIES - AWE ALDERMASTON - 16099
Graham Rogers, NSG Environmental Ltd (UK)
Decommissioning of Active Effluent Gantries AWE Aldermaston
BNS Nuclear Services (formerly Alstec) together with NSG Environmental Ltd have successfully undertaken the decommissioning
and removal of a redundant active effluent gantry system operated since the 1950s, however in a deteriorating condition,
at AWE Aldermaston. <strong>The</strong> 18 month, (30,000 man hour) project due for completion in March 2009, has been undertaken to programme
and without any lost time incidents / accidents.
<strong>The</strong> scope of work included:
• the design and erection of a purpose built size reduction and HHISO loading facility including HEPA filtered ventilation
system
• BPM and Environmental Impact Assessments
• Generation of novel methodology and Safe Systems of Work for the containedremoval of 1300metres of potentially ILW
stainless steel pipework at height
• Size reduction, assay and segregation of over 70 te steel, with approx 30% being consigned as free release for recycling
• Sampling and DQA assessments for the leveling and removal of 1800 m3 of earth
3) VERIFICATION TEST OF CLEARANCE AUTOMATIC LASER INSPECTION SYSTEM FOR SURFACE
CONTAMINATION MEASUREMENT - 16109
Michiya Sasaki, Haruyuki Ogino, Takeshi Ichiji, Takatoshi Hattori,
Central Research Institute of Electric Power Industry (Japan)
Recently, the clearance automatic laser inspection system (CLALIS) has been developed for clearance measurement of metal
scraps and concrete debris. It utilizes three-dimensional laser scanning, gamma-ray measurement and Monte Carlo calculation, and
its outstanding detection ability has been verified. In Japan, when an object is removed from a radiation-controlled area, the activity
level must be lower than the surface contamination density standard of 4 Bq/cm2 for beta and gamma emitters, which is onetenth
of the surface contamination density limit. According to the clearance inspection report published by the Nuclear Safety Commission
of Japan, the activity level of waste must be compared with not only the clearance level but also the surface contamination
density standard for clearance inspection. To demonstrate that CLALIS can also be used for the measurement of surface contamination,
a verification test was carried out using actual metal waste samples of various shapes, sizes and activity levels at the Kashiwazaki-Kariwa
Nuclear Power Station of Tokyo Electric Power Company. As a result, it was clarified that CLALIS gives a conservative
value for surface contamination compared with the conventional GM survey meter measurement since the activities of metal
waste samples were estimated using the total count rate, a fixed average surface area of 100 cm2 and the conservative source position
assumed in the Monte Carlo calculation for the calibration factor. In a nuclear power plant, the actual judgment of whether an
object can removed from a radiation-controlled area is based on whether the result of surface contamination measurement is lower
than the detection limit, which is significantly lower than 4 Bq/cm2. According to this criterion, CLALIS provides an almost identical
judgment to the GM survey meter, which means that CLALIS can be used as a rational clearance monitor to carry out clearance
level and surface contamination inspections in a single radiation measurement. <strong>The</strong> prospective detection limit for CLALIS at
nuclear power plants is also discussed and compared with that for the conventional surface contamination monitors
104

Abstracts Session 36
4) PRELIMINARY STUDY OF CRYOGENIC CUTTING TECHNOLOGY FOR DISMANTLING HIGHLY
ACTIVATED FACILITIES - 16006
Sung-Kyun Kim, Korea Atomic Energy Reserach Institute (Korea);
Dong-Gyu Lee, Kune-Woo Lee, Korea Atomic Energy Research Institute (Korea)
Cryogenic cutting technology is one of the most suitable technologies for dismantling nuclear facilities due to the fact that a
secondary waste is not generated during the cutting process. In this paper the feasibility of cryogenic cutting technology has been
investigated by using a computer simulation. In the computer simulation, a hybrid method combined with the SPH (smoothed particle
hydrodynamics) method and with the FE (finite element) method was used. And also, a penetration depth equation, for the
design of the cryogenic cutting system, was used and the design variables and operation conditions to cut a 10 mm thickness for
steel were determined. Finally the main components of the cryogenic cutting system were developed on the basis of the obtained
design values.
5) ABRASIVE BLASTING UNIT (ABU) - 16270
Georg Braehler, Philipp Welbers, NUKEM Technologies GmbH (Germany);
Gianfranco Brunetti, Diederik van Regenmortel, Joint Research Centre (Italy); Mike Kelly, Nuvia Limited (UK)
As active nuclear facilities outlive their useful life and are decommissioned, they produce considerable quantities of slightly
contaminated components. <strong>The</strong> burden of dealing with this waste in both an environmentally responsible and efficient way has been
a key factor that has driven the nuclear industry to seek solutions from wider industrial applications. <strong>The</strong> methods to reduce the
quantity of contaminated waste are becoming more refined as the remarkable economic benefits of decontamination and subsequent
recycling of materials are realised. Maximising the amount of material that can be released from a nuclear site, following decontamination
is a key achievement in view of environmental impact and waste disposal costs considerations. Dry decontamination
methods are preferred, due to lower volumes of secondary waste and their easier handling, as compared with wet methods.
NUKEM Technologies GmbH was contracted to supply a dry, automated drum belt (tumbling) Abrasive Blasting Unit (ABU)
to the Joint Research Centre (JRC) of the European Commission in Ispra/Italy. <strong>The</strong> ABU was installed in the centralised radioactive
waste management area of the JRC. <strong>The</strong> unit is to be employed for the decontamination to clearance levels of slightly contaminated
metal components and, where practical, concrete or heavy concrete (density ~3200kg/m3) blocks.
Among the several possibilities of adapting conventional abrasive units to nuclear applications, an automatic tumbling machine
was preferred, due to the larger output and (mainly) to the ease of operation, with minimum direct handling of contaminated material
by operators, thus satisfying the ALARA principle. Consideration was also given to Belgoprocess succesful experience with a
predecessor, similar unit.
6) DECOMMISSIONING OF THE A-1 NPP LONG-TERM STORAGE FACILITY - 16299
Jan Medved, VUJE, Inc. (Slovakia); Ladislav Vargovcik, ZTS VVU KOSICE a.s. (Slovakia)
<strong>The</strong> paper deals with experience, techniques and new applied equipment durig undergoing decommissioning process of the A-
1 NPP long-term pool storage and the follow-up decommissioning plan. For rad-waste disposal of the long-term pool storage
(where most of the contaminants had remained following the removal of spent fuel) special equipment has been developed,
designed, constructed and installed. <strong>The</strong> purpose of this equipment is the restorage, drainage and fragmentation of cartridges (used
as a spent fuel case), as well as treatment of sludge (located at the pool bottom) and of the remaining liquid radwaste.
<strong>The</strong> drainage equipment for cartridges is designed for discharging KCr2 solution from cartridges with spent fuel rods into the
handling storage tank in the short-term storage facility and adjustment of the cartridges for railway transport, prior to the liquidation
of the spent fuel rod. <strong>The</strong> equipment ensures full remote visual control of the process and exact monitoring of its technical
parameters, including that of the internal nitrogen atmosphere concentration value. Cartridges without fuel and liquid filling are
transferred to the equipment for their processing which includes fragmentation into smaller parts, decontamination, filling into
drums with their sealed closing and measurement of radioactive dose. For the fragmentation, special shearing equipment is used
which leaves the pipe fragment open for the following decontamination. For cleaning the cartridge bottom from radioactive sludge
water jet system is used combined with slow speed milling used for preparing the opening for water jet nozzle. <strong>The</strong> sludge from
the cartridge bottom is fixed into ceramic matrix.
7) USE OF FULL RECOVERY HYDROLASING EQUIPMENT FOR FACILITY DECOMMISSIONING - 16325
Scott Martin, Scott Adams, S.A.Robotics (USA)
<strong>The</strong> removal of surface contamination is a major challenge for nearly all nuclear facilities undergoing, or awaiting, decommissioning.
Conventional means of surface decontamination can expose workers to unnecessary hazards, and are often not fit-for-purpose
due to size constraints or weight restrictions. Additionally, conventional methods are not always easily deployed remotely due
to their complexity or required services. <strong>The</strong> use of ultra high pressure water for surface decontamination, known as hydrolasing,
is recognized as a technology which can be used in various applications requiring surface removal. Hydrolasing is an advantageous
technology for many reasons including its versatility, overall simplicity and relative ease of remote deployment.
For the nuclear industry, one of the largest challenges with regards to the use of hydrolasing is the requirement for the full
recovery of the injected water and removed solids. For non-nuclear applications, there is often no requirement for recovery of the
liquid and solid waste, which has led to few system designs which will recover the waste in full. S.A. Robotics experience with the
deployment of ultra high pressure water systems for nuclear applications has shown that full recovery of injected water and
removed solids is achievable in both underwater and in-air applications. Innovative equipment and system design have allowed S.A.
Robotics hydrolasing systems to achieve near 100% solid and liquid recovery during concrete hydrolasing. This technology has
been deployed for Fluor Hanford at Hanfords K-Basins, as well as for UKAEA as part of the Windscale Piles decommissioning
project.
<strong>The</strong> purpose of this paper is to provide a short description of the hydrolasing process and the associated waste issues, describe
the unique design features of S.A. Robotics hydrolasing systems which combat these issues, and provide an overview of two of the
hydrolasing projects that S.A. Robotics has completed.
105

Session 36-37 Abstracts
8) CURRENT ACTIVITIES OF ALLDECO AT DECOMMISSIONING OF THE A1 NPP - 16333
Jan Rezbarik, Stanislav Sekely, Jaroslav Katrlik, Dusan Majersky, All Deco s.r.o. (Slovakia)
<strong>The</strong> operation of the A1 NPP terminated as a consequence of an accident accompanied by serious fuel damage and internal
contamination of technological equipment. <strong>The</strong> decommissioning of the NPP is currently going on and planned to be finished by
2049. <strong>The</strong> specific conditions require a specific approach to the realisation of the decontamination and decommissioning works.
Many advanced technologies and equipment has been developed and applied to perform partial works. A great emphasis is put on
the thorough preparation of the work, verifying of the actual state, monitoring of the radiation situation, non-active training, optimisation
of working procedures and employment of remotely operated devices. <strong>The</strong> common aim of all these activities is the minimisation
occupational doses at optimal costs.
<strong>The</strong> character of the current works is demonstrated on some partial projects: removal and on-site solidification of radioactive
sludge, pre-treatment (reduction of specific activity) of some specific liquid radioactive wastes (dowtherm), pre-dismantling decontamination
and dismantlement of technological equipment, post-dismantling decontamination of segments and free release of the
materials.
SESSION 37 - D&D RADIOLOGICAL CHARACTERIZATION AND MONITORING
1) CRITICAL EVALUATION ON THE USE OF NON-DESTRUCTIVE AASSAY OF NUCLEAR PACKAGES
THROUGH DESTRUCTIVE BREAKDOWN AND INVENTORY RECOVERY - 16081
Stephen Hepworth, Rob Way, Sellafield Ltd (UK); Johathan Sharpe, VT Nuclear Services (UK)
Two historic waste packages on the Sellafield Site with potentially high fissile content were destined for re-packaging. Prior
to relocation and subsequent breakdown, each item underwent a campaign of non-destructive assay. <strong>The</strong> aim of the assay was to
gather information that would assist with the production of a safety case. <strong>The</strong> assay work consisted of: conventional x-ray radiography
to determine the identity of the contents; gamma imaging and three-dimensional tomographic re-construction to determine
the location of the gamma emitting material; and neutron coincidence counting coupled with gamma spectrometry to assign a fissile
mass.
Most items on the Sellafield Site that undergo non-destructive assay normally remain intact or are re-packaged with minimal
interference of the content. However, in this instance each item was dismantled and the fissile material recovered. This paper provides
a comparison of the measured results with the actual results for each technique.
<strong>The</strong> x-ray radiographic information was used to construct a three dimensional representation of the contents of each item. This
information was useful in identifying the plant items contained within. <strong>The</strong> results were discussed with plant operators who were
familiar with the historic plant. <strong>The</strong> operators were able to identify areas of likely accumulations of fissile material.
<strong>The</strong> two-dimensional gamma survey and subsequent three-dimensional re-construction revealed the location of the gamma
emitting materials within the packages. It was assumed that areas of increased gamma activity indicated areas of increased fissile
mass.
2) DECOMMISSIONING OF A VITRIFICATION FACILITY: RINSING PHASE - 16231
Marielle Asou, CEA (France); Sebastien Leblanc, Fabrice Bouchet, Franck Martin, AREVA (France)
<strong>The</strong> Marcoule site was the host of the very first electricity-generating nuclear reactors (3 gas-graphite reactors operated
between 1956 and 1984) and spent fuel reprocessing plant (UP1 and various ancillaries operated between 1958 and 1997). Reprocessing
plant has been shut down ten years ago and since this time decommissioning, dismantling and waste retrieval activities is
under way.
An important part of this decommissioning program concerns the vitrification facility of Marcoule. This facility includes 20
tanks devoted to interim storage of highly active solutions, awaiting for vitrification.
<strong>The</strong> main objectives of the rinsing phase are to decrease activity in equipment before dismantling and to minimize the amount
of highly radioactive waste resulting from rinsing, which are to be vitrified.
3) THE LEVEL OF UNCERTAINTY IN MATERIALS CLEARANCE - 16090
Peter Burgess, Nuvia (UK)
Measurement of surface levels is essential in waste assessment and in clearing materials from nuclear licensed sites. Radiation
measurements in general are much less accurate than most forms of engineering measurement, even in relatively simple conditions,
such as radiochemical laboratories. Waste assessment during clearance is far more difficult. <strong>The</strong> areas of uncertainty include: (1)
<strong>The</strong> intrinsic limitations of the equipment employed. For surface activity measurement, the detector is often a large area alpha +
beta scintillation probe connected to a ratemeter. Any detector has an effective energy threshold below which it fails to register an
event. <strong>The</strong> detector response is rarely uniform over the window area. <strong>The</strong> detector is connected to a ratemeter. <strong>The</strong> design of a
ratemeter and the way it is set up will have a large influence on how easy the user finds it to classify correctly materials close to
the exempt limit.. (2)Calibration of the equipment. <strong>The</strong>re is only a limited set of surface contamination sources available. Prediction
of the response to other nuclides can be complicated. (3)Determination of the fingerprint. For many practical situations, the
potential contaminant is a mixture of nuclides emitting a mixture of alpha, beta, gamma and X radiation. Any detector will have a
response which depends on the radiation type and energy. Frequently, the response to the fingerprint of the most operationally
robust and convenient detectors will be dominated by only a small fraction of the total activity present. It is thus vital that that fraction
is well established and any area zoned so that the fraction remains reasonably stable. (4)<strong>The</strong> influence of natural activity in
materials and of gamma radiation from elsewhere. Many building materials have levels of natural activity in the Bq/g region. <strong>The</strong>se
often vary significantly from sample to sample and area to area, particularly where buildings and equipment have been extended
or modified. (5)Surface condition. For short range emissions such as alpha particles and low energy betas, the range for detection
in air is a few mm. Any material covering the activity, such as paint or grease, will reduce the emission rate.
106

Abstracts Session 37
4) ENVIRONMENTAL REMEDIATION AND USING A NEW SORTING AND FREE RELEASE SYSTEM
FOR CONTAMINATED SOIL AT NPP A1 SITE, SLOVAKIA - 16020
Ondrej Slavik, Miroslav Baca, Alojz Slaninka, VUJE, a.s. (Slovakia);
Stanislav Janecka, Camberra Packard (Slovakia); Ján Sirota, JAVYS, a.s. (Slovakia)
Environmental remediation at NPP A1 site is even presently a continual process of removing the contamination from the
ground or auxuliary objects within the NPP A-1 site with accidentally shut down reactor. This paper mainly deal with monitoring,
sorting out and disposal of large volumes of removed contaminated soil stored temporarily until now at the site which is necessary
for enhancement of environmental radiation situation at the site. It was also one of the topic of the Decommissioning Project of
NPP A1, Slovakia, - Phase No I, lasted from 1999 to 2008. Within the project, attention was paid to development of technical tools
for handling with and monitoring of large volume of contaminated soil, as well. Besides short description of contaminated lands at
the site, sources of their contamination and to date known inventory, details of a pilot contaminated soil sorting facility developed
and tested recently within the Decommissioning project will be described and discussed in the papper. <strong>The</strong> paper topics include
description of and uncertainty analysis results for the pilot soil sorting system based on the Canberra-Packard pilot conveyer belt
monitor with a pair of 1.5 inch LaBr scintilation detectors and integrated electronic belt scale. In addition experiences learned during
the metrological testing and operational trial will be summarised. MDA for Cs-137 of this system is 140 Bq/kg for 30 kg and
50 Bq/kg for 300 kg parts of soil at 500 Bq/kg of 40K and 0.15 mikroGy/h.
5) THE USE OF RADIOLOGICAL CHARACTERISATION IN SUPPORT OF THE DESIGN AND BUILD
OF A NEW FACILITY IN AN AREA OF ELEVATED DOSE RATE - 16009
Karl Hughes, David Thornley, VT Nuclear Services Ltd (UK);Czeslaw Pienkowski, Sellafield Ltd. (UK)
A new building, a maintenance facility, is to be constructed in the separation area of the Sellafield Site. Sellafield is a complex
and busy nuclear facility covering about 2 square miles in the north-west of the United Kingdom. <strong>The</strong> facility, which is to provide
necessary storage and maintenance functionality to support bulk waste retrievals from legacy silos, is being built in close proximity
to spent fuel storage ponds, intermediate level legacy waste stores and a pipebridge carrying active materials. In addition, the
site is adjacent to a main pedestrian and vehicle thoroughfare and a railway line used for the regular transfer of nuclear materials.
<strong>The</strong> facility itself is to be built on the site of a recently demolished active facility.
<strong>The</strong> ambient gamma dose rates in the construction area have been measured to be typically 5 to 50 microSv/hr. Although there
are known specific sources of dose rate close to the construction site, the relative contributions of each within the envelope of the
new facility are unknown.
This paper describes how a series of gamma dose rate measurements, gamma spectroscopy measurements and gamma-ray
imaging surveys, using RadScan® 800, have been used to better understand the origins of the dose rates at a number of key locations
within the area
6) THE APPLICATION OF ADDITIONAL, OFF-LINE, ANALYSIS TECHNIQUES TO PCM MONIT
OR RESULTS TO AID THE EFFICIENT AND COST EFFECTIVE REPACKAGING OF
LEGACY PCM WASTES CONTAINING PLUTONIUM FLUORIDE - 16034
David Thornley, Kareena McCrindle, Stephen Rayner, Jonathan Sharpe, VT Nuclear Services (UK);
Czeslaw Pienkowski, Carl Phillips, Sellafield Ltd (UK)
<strong>The</strong>re are a small number of legacy, orphan waste, PCM (Plutonium Contaminated Material) drums at Sellafield Site containing
calcium metal potentially contaminated by plutonium (Pu), some of which may be in the form of plutonium fluoride (PuF4).
<strong>The</strong>se drums were measured on a TRU-D® PCM Drum Monitor to give a Nuclear Safety value for the Pu mass based on Neutron
Coincidence Counting (NCC) and the Pu isotopic composition measured for each drum using a germanium detector based High
Resolution Gamma Spectrometry system.
In some circumstances the presence of Pu in the form of PuF4 can cause a significant overestimate of the measured Pu mass.
This is as a result of alphas emitted by the spontaneous decay of Pu isotopes interacting with light elements such as fluorine, resulting
in the emission of random(alpha, n) neutrons. <strong>The</strong> potential overestimate may be very large for total neutron counting based
systems if the presence of PuF4 is not accounted for in the system calibration. However, significant quantities of PuF4 may also
result in overestimates for NCC systems due to potentially large statistical uncertainties in the measurement results caused by accidental
coincidences involving the random (alpha,n) neutrons. <strong>The</strong>refore in some circumstances, less pessimistic measurements may
be obtained from the total neutron count, corrected using the measured PuF4 ratio.
7) THE RADIOACTIVITY DEPTH ANALYSIS TOOL (RADPAT) - 16144
Alan Shippen, Malcolm Joyce, Lancaster University (UK)
<strong>The</strong> Radioactive Depth Analysis Tool (RADPAT) is a PhD bursary project currently being undertaken at Lancaster University
in the UK. <strong>The</strong> RADPAT project involves the development of nuclear instrumentation capable of ascertaining depth of radioactive
contamination within legacy plant materials such as concrete. This paper evaluates the merits of two types of detector; sodium
iodide (NaI(Tl)) and cadmium zinc telluride (CZT), both of which have been identified as possible solutions for the final RADPAT
detector. A bespoke concrete phantom has been developed to allow a set depth of simulated contamination to be obtained with a
low measurement error within a concrete analogue: silica sand. Utilising this phantom, in combination with the selected detectors,
a set of measurements have been obtained varied with increasing depth of caesium-137 contamination. By comparing the relative
attenuation of the x-ray and g-ray photopeaks from the data-set to that suggested by a differential attenuation law, a set of model
parameters can be obtained. This model, once calibrated, describes the contact depth of contamination with the relative intensity of
the peaks in a measured spectrum with a high degree of accuracy. Thus, this technique allows for a set of measurements across the
surface of a given material to obtain the inherent distribution of the depth of caesium-137 contamination. This paper is primarily
interested in the ability of each detector type to derive the attenuation model, paying particular attention to the associated statisti-
107

Session 37-38 Abstracts
cal uncertainty of the fitted parameters and thus the error in the derived depth. <strong>The</strong> paper describes the contributing effects of the
inherent prop- Address all correspondence to this author. erties of each detector; effects such as their energy resolution, absolute
efficiency as well as peak-to-Compton ratio. Finally a commentary on the applicability of each selected detector type is presented,
including a comment on the extension the technique to a more generic, real world solution.
8) REMOTE MEASUREMENTS OF RADIOACTIVITY DISTRIBUTION WITH BROKK ROBOTIC SYSTEM - 16147
Oleg Ivanov, Alexey Danilovich, Vyacheslav Stepanov, Sergey Smirnov, Victor Potapov, RRC Kurchatov Institute (Russia)
Robotic system for the remote measurement of radioactivity in the reactor areas was developed. <strong>The</strong> BROKK robotic system
replaces hand-held radiation measuring tools. <strong>The</strong> system consists of a collimated gamma detector, a standard gamma detector,
color CCD video camera and searchlights, all mounted on a robotic platform (BROKK). <strong>The</strong> signals from the detectors are coupled
with the video signals and are transferred to an operator’s console via a radio channel or a cable. Operator works at a safe position.
<strong>The</strong> video image of the object with imposed exposure dose rate from the detectors generates an image on the monitor screen,
and the images are recorded for subsequent analysis. Preliminary work has started for the decommissioning of a research reactor
at the RRC «Kurchatov Institute». Results of the remote radioactivity measurements with new system during radiation inspection
waste storage of this reactor are presented and discussed.
9) RADIOLOGICAL CHARACTERISATION THROUGHOUT THE UK NUCLEAR INDUSTRY - 16300
Chris Hannon, Studsvik UK (UK)
Radiological Characterisation is the technique of determining the radiological properties of a material using a combination of
studying the materials history, in-situ measurements and intrusive sampling.
To consign radioactive waste from a site in the UK knowledge of the wastes radiological content is required. Intermediate
Level Waste (ILW), Low Level Waste (LLW), exempt and excluded materials all require characterisation to different degrees and
certainty. Effective radiological characterisation will determine the most suitable waste treatment or disposal route. Money spent
by a project on characterisation up front will be recouped in the long term by efficient waste sentencing.
<strong>The</strong> first step in any campaign of radiological characterisation is to study the available information relating to the history of
the waste. By carefully studying the history of he waste the most likely waste treatment/disposal routes can be identified and the
most applicable types of in-situ measurements or intrusive sampling can be derived. Whilst it is not uncommon to have little or no
reliable historic information a logical and defensible hypothesis of the wastes likely classification can streamline the characterisation
project. However care must always be taken to not limit the types of measurements that will be undertaken so as to limit the
risk of missing some hard to measure radionuclides.
SESSION 38 - SITING, DESIGN, CONSTRUCTION, AND OPERATION OF L/ILW DISPOSAL FACILITIES
1) DESIGN OPTIONS FOR THE UKS ILW GEOLOGICAL DISPOSAL FACILITY - 16241
Tim Hicks, Matt White, Tamara Baldwin, Paul Hooker, Phil Richardson, Galson Sciences Ltd (UK); Neil Chapman,
Chapman & Co. Consulting (Switzerland); Fiona Neall, Neall Consulting Ltd (UK);
Ian McKinley, McKinley Consulting (Switzerland); Samantha King, NDA RWMD, (UK)
Over the last few years, a major national programme of public consultation has been under way in the UK resulting, in 2006,
in the announcement by government of geological disposal as the most appropriate solution for the long-term management of the
UKs long-lived and higher-activity radioactive waste and the launch, in 2008, of an implementation programme. <strong>The</strong> approach
being pursued is to solicit volunteer communities to host a geological disposal facility, which may contain not only intermediatelevel
waste (ILW) and some low-level waste (LLW), but also high-level waste (HLW), any spent fuel (SF) declared as waste, and
potentially other materials that may be declared as waste. <strong>The</strong>se wastes have different physical, chemical, thermal and radiological
characteristics, and different concepts will be required to accommodate their disposal, potentially in a single facility.
<strong>The</strong> volunteer approach means that the geological environment that might eventually emerge as the preferred location is not
known at the outset. Indeed, the siting process may require evaluation of several different geological environments because the UK
has rich geological variability for such a small landmass. Consequently, the Nuclear Decommissioning Authority (NDA), which is
charged with designing, developing and implementing a geological disposal facility, has investigated facility designs that could be
appropriate for a wide range of host rocks and geological environments.
2) LESSONS LEARNED FROM THE OPERATION OF A L/ILW NATIONAL DISPOSAL CENTRE:
THE CABRIL AND THE SPANISH CASE - 16029
Emilio Garcia Neri, Mariano Navarro, Fernando Gomez,ENRESA (Spain)
<strong>The</strong> Spanish experience holds a relatively important position in the field of the LILW management.
<strong>The</strong> management of LILW in Spain can be defined as an integrated system that includes from the controls of production and
the collection and transport of LILW to its disposal. In this system, the clear definition of the responsibilities of each one of the
actors has a fundamental paper.
ENRESA, the Radioactive Waste Management Organisation in Spain, operates the El Cabril centre from 1993, being this
installation a key component for the National LILW management programme.
Throughout these years, ENRESA is accumulated a significant operational experience from a multidisciplinary point of view,
that includes technical, economic and social aspects. From his phase of design to today, passed already more than fifteen years,
ENRESA has adopted a series of decisions and developed programs and activities that have allowed the evolution of the own installation
until the reality that is today.
This paper intends to present the lessons learned through this experience from a strategic perspective on more relevant and significant
aspects that they have facilitated the normal operation of the installation and the development of specific solutions to the
challenges proposed by the development of the activities and the new needs of the Spanish programme.
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Abstracts Session 38
3) HYDROGEOLOGIC MODELLING IN SUPPORT OF A PROPOSED DEEP GEOLOGIC REPOSITORY IN
CANADA FOR LOW AND INTERMEDIATE LEVEL RADIOACTIVE WASTE - 16264
Jonathan Sykes, Stefano Normani, Yong Yin, University of Waterloo (Canada);
Eric Sykes, Mark Jensen, Nuclear Waste Management Organization (Canada)
A Deep Geologic Repository (DGR) for Low and Intermediate Level radioactive waste has been proposed by Ontario Power
Generation for the Bruce Nuclear Power Development site in Ontario, Canada. <strong>The</strong> DGR is to be constructed at a depth of about
680 m below ground surface within the argillaceous Ordovician limestone of the Cobourg Formation. This paper describes a regional-scale
geologic conceptual model for the DGR site and analyzes flow system evolution using the FRAC3DVS-OPG flow and
transport model. This provides a framework for the assembly and integration of site-specific geoscientific data that explains and
illustrates the factors that influence the predicted long-term performance of the geosphere barrier. In the geologic framework of the
Province of Ontario, the Bruce DGR is located at the eastern edge of the Michigan Basin. Borehole logs covering Southern Ontario
combined with site specific data have been used to define the structural contours at the regional and site scale of the 31 sedimentary
strata that may be present above the Precambrian crystalline basement rock. <strong>The</strong> regional-scale domain encompasses an 18,500
km2 region extending from Lake Huron to Georgian Bay. <strong>The</strong> groundwater zone below the Devonian is characterized by units containing
stagnant water having high concentrations of total dissolved solids that can exceed 300 g/l. <strong>The</strong> computational sequence
involves the calculation of steady-state density independent flow that is used as the initial condition for the determination of pseudo-equilibrium
for a density dependent flow system that has an initial TDS distribution developed from observed data. Long-term
simulations that consider future glaciation scenarios include the impact of ice thickness and permafrost. <strong>The</strong> selection of the performance
measure used to evaluate a groundwater system is important. <strong>The</strong> traditional metric of average water particle travel time
is inappropriate for geologic units such as the Ordovician where solute transport is diffusion dominant. <strong>The</strong> use of life expectancy
and groundwater age is a more appropriate metric for such a system. <strong>The</strong> mean life expectancy for the DGR and base case parameters
has been estimated to be in excess of 8 million years.
4) I-GRAPHITE WASTE MANAGEMENT IN FRANCE - 16301
Odile Ozanam, Gerald Ouzounian, ANDRA (France)
In France about 23,000 tons of irradiated graphite waste were generated mainly from 9 nuclear gas-cooled reactors (UNGG
type). All these reactors are now shut down. In France, a final disposal route has been decided for i-graphite waste management by
the French Parliament in 2006. <strong>The</strong> planning act of June 28, 2006 has provisioned that a research and investigation programme shall
be established with a view to developing disposal options for graphite waste.
<strong>The</strong> low specific activity of these wastes means shallow disposal facilities located in a geological layer with a low permeability.
<strong>The</strong> main radionuclides that need specific attention for the long term safety are Chlorine 36 and Carbon 14. This establishes the
main requirements for the graphite disposal. According to these requirements, underground disposal in a clay layer, at shallow
depth, offers good performance in terms of the delay and the reduction of the radionuclide release; it also offers guarantees for the
cover’s hydrodynamic and transport properties.
<strong>The</strong> progress of the programme makes it now necessary for a site to be found. Based on a bibliographical study, a wide-spread
call for applications took place during the second semester of 2008.
5) INDUSTRIAL COMPLEX FOR SOLID RADWASTE MANAGEMENT (ICSRM) AT CHERNOBYL NUCLEAR
POWER PLANT FUNCTIONALITY OF THE FACILITIES - EXPERIENCE OF PROJECT EXECUTION - 16057
Heiko Eichhorn, NUKEM Technologies GmbH (Germany)
After an international tendering process NUKEM was awarded to build the Industrial Complex for Solid Radwaste Management
(ICSRM) at the Chernobyl Nuclear Power Plant. <strong>The</strong> ICSRM consists of four facilities (LOT): Lot 0: SLWS (Solid and Liquid
Waste Storage) It is an interim storage facility for intermediate and high level long-lived radioactive waste in an existing building
at ChNPP site. This building has been refurbished and modified to accommodate the required equipment. LOT 0 was handed
over to the Employer June 2007 LOT 1: A solid waste retrieval facility, comprising the installation of a retrieval facility for operational
Low and Intermediate Level Short-Lived Waste (LILW-LL/SL) and High Level Waste (HLW) currently stored in the existing
storage silo. Due to the Chernobyl accident, this storage also contains an unknown percentage of Long-Lived (LL) waste. LOT
1 was handed over to the Employer in April 2009. LOT 2: solid waste processing plant, comprising a plant for the sorting and segregation
of all categories of solid radwaste and the processing of the solid LILW-LL/SL generated from the previous retrieval activities
(LOT 1) and from the routine operational and decommissioning activities of the ChNPP. LILW-SL will be packaged and immobilized
for removal to the near surface disposal facility (LOT 3) whilst higher category wastes (LILW-LL and HLW) will be packaged,
over-packed and stored in a temporary storage facility (SLWS) while awaiting the construction of an interim storage facility.
LOT 2 is handed over to the Employer in April 2009. LOT 3: repository for the disposal of short-lived waste, comprising a near
surface repository in accordance with the requirements of the Ukrainian Nuclear Regulatory Authorities and in the form of an engineered
facility for the final disposal of LILW-SL conditioned in LOT 2 and for wastes from the Liquid Radwaste Treatment Plant
(LRTP) currently being build on Chernobyl NPP site. <strong>The</strong> facility will maintain its integrity during 300-year instutional control period.
LOT 3 was handed over to the Employer in December 2007.
6) EXPERIENCES RELATED TO THE DEVELOPMENT OF A HIGH VOLUME VERY LOW LEVEL WASTE
DISPOSAL FACILITY IN THE UK - 16371
Andy Baker, Andy Baker Consulting Ltd (UK); Andrea Borwick,WRG (UK); KayLin Loveland, Adam Meehan,
Mike Travis, EnergySolutions (UK); Ian Warner, Magnox North Ltd (UK)
New Government policy regarding waste disposal suggests that a wider range of options should be evaluated for the management
of low-level waste (LLW), including disposal to landfill. A new sub-category was created for nuclear industry waste disposal:
high-volume very low level waste (HV VLLW). <strong>The</strong> Government has stated that it expects the majority of waste in this category
that could go to landfill would consist of rubble and soil from decommissioning activities. This category would contain only
small amounts of radioactivity and can be safely disposed to landfill, subject to appropriate controls.
109

Session 38-39 Abstracts
In response to this policy change, Waste Recycling Group (WRG) and EnergySolutions have engaged in developing one of
the first private HV VLLW landfills in the UK at the WRG Lillyhall facility in West Cumbria, UK. This paper describes the
approach that we have followed in developing proposals for the site, including: our review and understanding of revised Government
policy; site selection, including the evaluation of environmental factors, location, and capacity; our approach to applying for
an authorisation; dealing with stakeholder involvement and communications; regulatory dialogue; the development of waste acceptance
criteria; the development of operational procedures; and site commissioning.
7) ESTABLISHING A SITE FOR A SLOVENIAN L/ILW REPOSITORY - 16151
Sandi Viršek, Janja Ŝpiler, Miran Veselič, ARAO (Slovenia)
In this paper we will describe the practice and siting process for a LILW repository in Slovenia. Slovenia is a small country,
and, consequently, its nuclear programme is small. It does include almost everything that large programmes have, but we still do
not have a repository. In 2004, the Slovenian Radwaste management agency (ARAO) initiated a new procedure to find a proper
location for a LILW repository. ARAO asked all Slovenian communities to participate. All communities have the option to withdraw
from the process until they have approved the site. We received eight responses, and we prepared methodologies with different
parameters to evaluate all potential sites. All sites were assessed by Slovenian experts, and determinations were based on using
prepared methodologies. On the basis of their expert opinions, we prepared a prefeasibility study and chose the three most suitable
sites. With these three we continued the process. After that time, one of the communities withdrew from the procedure, and another
one reversed its proposed site and proposed a new one. For the third site we continued with the programme, and we prepared a
feasibility study with a Strategic Environmental Impact Assessment and preliminary safety calculations for the comparison of different
concepts of disposal units. If everything goes according to the plan for this site and the concept, we expect site approval in
the first half of 2009. After that, we will start preparing everything necessary for building permission.
SESSION 39 - L/ILW WASTE HANDLING, TECHNOLOGIES, AND DATA ANALYSIS - PART 1 OF 3
1) IMPROVED PRACTICES FOR PACKAGING TRANSURANIC WASTE AT LOS ALAMOS NATIONAL
LABORATORY (LA-UR-09-03293) - 16280
Kapil Goyal, Peter Carson, Los Alamos National Laboratory (USA)
Transuranic (TRU) waste leaving the Plutonium Facility at Los Alamos National Laboratory (LANL) is packaged using
LANLs waste acceptance criteria for onsite storage. Before shipment to the Waste Isolation Pilot Plant (WIPP) in southeastern New
Mexico, each payload container is subject to rigorous characterization to ensure compliance with WIPP waste acceptance criteria
and Department of Transportation regulations. Techniques used for waste characterization include nondestructive examination by
WIPP-certified real-time radiography (RTR) and nondestructive assay (NDA) of containers, as well as headspace gas sampling to
ensure that hydrogen and other flammable gases remain at safe levels during transport. <strong>The</strong>se techniques are performed under a rigorous
quality assurance program to confirm that results are accurate and reproducible. If containers are deemed problematic, corrective
action is implemented before they are shipped to WIPP.
A defensive approach was used for many years to minimize the number of problematic drums. However, based on review of
data associated with headspace gas sampling, NDA and RTR results, and enhanced coordination with the entities responsible for
waste certification, many changes have been implemented to facilitate packaging of TRU waste drums with higher isotopic loading
at the Plutonium Facility at an unprecedented rate while ensuring compliance with waste acceptance criteria.
This paper summarizes the details of technical changes and related administrative coordination activities, such as information
sharing among the certification entities, generators, waste packagers, and shippers. It discusses the results of all such cumulative
changes that have been implemented at the Plutonium Facility and gives readers a preview of what LANL has accomplished to
expeditiously certify and dispose of newly generated TRU waste.
2) RADIOLOGICAL ASSESSMENT OF PETROLEUM PIPE SCALE WASTE STREAMS
FROM DRY-RATTLING OPERATIONS - 16323
Ian Hamilton, Foxfire Scientific, Inc. (USA); Robert Berry,Matthew Arno, Erich Fruchtnicht, Foxfire Scientific (UK)
Petroleum pipe scale consists of inorganic solids, such as barium sulfate. <strong>The</strong>se solids can precipitate out of brine solutions that
are pumped out of oil wells as part of normal oilfield operations. <strong>The</strong> precipitates can nucleate on down hole pipe walls, causing
the buildup of hard scales in some tubulars in a pipe string, while leaving others virtually untouched. Once the scale buildup is sufficient
to restrict flow in the string significantly, the tubulars are removed from service. Once removed, tubulars are transported to
storage yards for storage, subsequent inspection, and possible recycling.
Many of the tubulars are never returned to service, either because threads are too damaged, or pipe walls are too thin, or the
scale buildup is too thick. <strong>The</strong> tubular refurbishment industry uses primarily one of two processes, either a high-pressure water
lance or a dry, abrasive “rattling” process to ream pipes free of scale buildup. Historically, the dry rattling process has been used
primarily for touching up new pipes that have rusted slightly during storage; however, pipes with varying levels of scale have been
reamed, leaving only a thin coating of scale on the inner diameter, and then returned to service.
3) THE DIAMOND UNIVERSITY RESEARCH CONSORTIUM: NUCLEAR
WASTE CHARACTERISATION, IMMOBILISATION AND STORAGE - 16374
Simon Biggs, Michael Fairweather, James Young, University of Leeds (UK);
Neil Hyatt, University of Sheffield (UK); Francis Livens, <strong>The</strong> University of Machester (UK)
Legacy waste treatment, storage and disposal, as well as decommissioning and site remediation, from the UKs civil nuclear
programme are estimated at a cost of £70B. <strong>The</strong> Nuclear Decommissioning Authority (NDA) directs the strategy for all civil nuclear
decommissioning, with demanding timescales now set for all nuclear sites. Additionally, the Committee on Radioactive Waste Management
(CoRWM) recently delivered a recommendation, accepted by Government, that geological disposal in a mined repository
presents the best available approach for long term management of the waste legacy.
110

Abstracts Session 39-40
<strong>The</strong>re is therefore a requirement to decommission all power generation and experimental reactors, and fuel reprocessing plants,
to decontaminate land, and to return nuclear licensed sites to brown or green field status. <strong>The</strong> engineering and scientific challenges
that lie ahead in meeting these targets are significant, and many of the ideas required to deliver the final end state have not yet been
researched. In recognition of this in 2007 the UK Research Councils Energy Programme released a call for research proposals in
the area of nuclear waste management and decommissioning valued at £4M. A grant was subsequently awarded in 2008 to a consortium
led by the University of Leeds, with member universities from Manchester, Imperial College, Sheffield, Loughborough and
University College London.
4) THE NEW EDF TRACKING SYSTEM - 16292
Emmanuelle Julli, Bertrand Lantes, EDF (France)
EDFs network of nuclear power plants (NPP) comprises 58 pressurized water reactors. Solid waste arising during plant operation
(mainly VLLW, LLW and ILW) are conditioned and sent either to interim storage, an off site treatment plant for additional
processing (e.g. the Centraco incinerator or the melting facilities of SOCODEI) or directly to one of the two final repositories operated
by ANDRA, the French national radioactive waste management agency.
<strong>The</strong> tracking system allows:
• the checking of waste package characteristics against acceptance criteria of the final disposal facilities or off site treatment
facilities; and
• the transmission of the waste package data to ANDRA and SOCODEI.
Since 1992, the EDF computer application DRA has been run on networked computers at EDF and ANDRA, and more recently
at SOCODEI.
SESSION 40 - L/ILW WASTE HANDLING, TECHNOLOGIES, AND DATA ANALYSIS - PART 2 OF 3
1) CHARACTERIZATION OF THE RADIOCHEMICAL ACTIVITY IN CANDU STEAM GENERATORS - 16204
Aamir Husain, Yury Verzilov, Sriram Suryanarayan, Kinectrics,Inc. (Canada)
<strong>The</strong> scope of mid-life refurbishment activities at some CANDU plants includes replacement of the existing steam generators.
Shipment of the discarded steam generators for interim storage, intact disposal or for recycling via metal melting requires an assessment
of dose rates and the inventory of radionuclides within the components. Kinectrics was contracted by CANDU utility owners
to develop such data.
This paper presents the detailed methodology employed to develop dose rate and radionuclide inventory data for radionuclides
within both in-service and the out-of-service (in-storage) steam generators. <strong>The</strong> data were developed as follows: a) archived tube
sections from various steam generators were characterized; scaling factors were derived using the detailed alpha and beta activity
data obtained, b) in-situ gamma spectrometry (using germanium and cadmium zinc telluride detectors) and dose rate surveys were
performed at various steam generators and c) a detailed assessment of the tritium inventory in various primary and secondary side
components was performed.
2) IMPROVED ALGORITHM FOR CLOSE GEOMETRY CHARACTERIZATION
OF WASTE USING GAMMA-RAY SPECTROSCOPY - 16320
John Guo, Richard Hagenauer, ORTEC-AMETEK (USA);Ronald Keyser, ORTEC – AMETEK (USA)
Proper characterization of waste is important to reduce the costs of disposal. <strong>The</strong> requirement for short data collection time
often means putting the detector as close to the waste container as possible. Nondestructive assay of gamma-ray emitting nuclear
waste requires modeling because preparing a standard to match the physical and radiological properties of any waste item is not
possible. Several assumptions must be made about the waste. Many models use simplified efficiency determinations and attenuation
corrections. <strong>The</strong>se models work well for medium-sized items when the detector-to-container distance is at least half of the
largest dimension of the object. Other models use a hybrid Monte Carlo approach, still using the container assumptions, but using
a complete set of measured detector efficiency parameters. A new algorithm for calculating the detector efficiency has been developed
to allow close-in (high efficiency) detector placement without extensive detector characterization, while retaining acceptable
accuracy of the analysis results. This algorithm uses a simple mixed-nuclide gamma calibration, the HPGe detector description
(crystal diameter and length, crystal type (n-type or p-type), thickness of germanium dead layer, and distance from the top of the
end cap to the crystal) to compute the intrinsic detector efficiency. <strong>The</strong> intrinsic detector efficiency for the front and side of the
detector are related to the detector diameter and length. <strong>The</strong> efficiency and corrections for the gamma rays from the item being
measured are calculated in a voxel-by-voxel manner. A new collimator correction algorithm has also been developed for close
geometry measurements. <strong>The</strong>se new algorithms have been implemented in the ISOTOPIC software. Results show significant
improvement for large boxes (B-25 box or larger) and items counted as close as 10 cm. Results from low-level drum counter measurements
show useful improvements.
3) FIELD EXAMPLES OF WASTE ASSAY SOLUTIONS FOR CURIUM-CONTAMINATED WASTES - 16259
Patrick Chard, Canberra UK Ltd. (UK); Barrie Greenhalgh, Sellafield Ltd. (UK);
Ann Ross, Dounreay Site Restoration Limited (DSRL) (UK); Tom Turner, UKAEA (UK);
Ian Hutchinson, Canberra UK Ltd (UK); Stephen Croft, Canberra Industries Inc. (USA)
Passive neutron coincidence counting is a mature technique for the assay of Pu in nuclear material. It is widely deployed in
safeguards and waste inventory verification applications.
<strong>The</strong> presence of 242Cm and 244Cm in spent fuel wastes, often poses a severe challenge owing to the relatively short spontaneous
fission half-life for these isotopes and the subsequent prolific spontaneous fission neutron emission. This is a well documented
problem, compounded by the fact that for most waste assay applications, neutron assay techniques are not capable of distinguishing
between these Cm isotopes and the even isotopes of Pu, which are normally of interest in waste assay applications. <strong>The</strong>refore
the presence of even small quantities of these isotopes can result in gross over-estimation of the Pu inventory, if an appropriate correction
is not made.
111

Session 40-41 Abstracts
Previous theoretical studies carried out recently have illustrated the potential magnitude of the problem, with reference to the
fundamental nuclear data and typical isotopic compositions of wastes. Neutron multiplicity counting can, in principle, differentiate
between isotopes that undergo spontaneous fission, however in practice the uncertainties in waste assay are such that this is rarely
beneficial. More practical “compensation” techniques use combinations of different assay techniques (for example passive and
active neutron counting) and knowledge of the actinide ratios in the waste stream fingerprint.
In this paper we describe various waste assay applications as case studies. For each example we describe the nature of the challenge
and show how solutions have been developed for applications where the presence of curium has caused problems. We
describe the technical solutions, showing the limitations and assumptions of each. We also emphasise the role of robust Quality
Assurance procedures, to ensure that the techniques are implemented reliably and with predictable outcomes. Finally, we describe
the benefits that have been realised for the plant operations teams, with regard to improved measurement accuracy, avoidance of
false over-estimation of the Pu inventory and subsequent improvement in plant throughput.
4) THEORETICAL MODELLING OF NUCLEAR WASTE FLOWS - 16377
J.F. Adams, S.R. Biggs, M. Fairweather, D. Njobuenwu and J. Yao, University of Leeds (UK)
A large amount of nuclear waste is stored in tailings ponds as a solid-liquid slurry, and liquid flows containing suspensions of
solid particles are encountered in the treatment and disposal of this waste. In processing this waste, it is important to understand
the behaviour of particles within the flow in terms of their settling characteristics, their propensity to form solid beds, and the resuspension
characteristics of particles from a bed. A clearer understanding of such behaviour would allow the refinement of current
approaches to waste management, potentially leading to reduced uncertainties in radiological impact assessments, smaller
waste volumes and lower costs, accelerated clean-up, reduced worker doses, enhanced public confidence and diminished grounds
for objection to waste disposal.
Mathematical models are of significant value in nuclear waste processing since the extent of characterisation of wastes is in
general low. Additionally, waste processing involves a diverse range of flows, within vessels, ponds and pipes. To investigate experimentally
all waste form characteristics and potential flows of interest would be prohibitively expensive, whereas the use of mathematical
models can help to focus experimental studies through the more efficient use of existing data, the identification of data
requirements, and a reduction in the need for process optimisation in full-scale experimental trials. Validated models can also be
used to predict waste transport behaviour to enable cost effective process design and continued operation, to provide input to
process selection, and to allow the prediction of operational boundaries that account for the different types and compositions of particulate
wastes.
SESSION 41 - TRANSPORTATION AND STORAGE OF HLW, FISSILE, TRU, AND SNF
1) EXPERIENCE WITH DRY CASK STORAGE TECHNOLOGY IN GERMANY - 16416
Heinz Geiser, Jens Schroeder, Dietrich Hoffmann, GNS mbH (Germany)
In Germany spent fuel will exclusively be disposed of in deep geological formations. Until the availability of a final repository,
spent fuel assemblies (SFA) are mainly stored in casks of the CASTOR® type which constitute dual-purpose casks for transport
as well as for storage. For the storage of these casks, interim storage facilities (ISF) have been constructed on the sites of each
nuclear power plant (NPP) in Germany. In the meantime GNS has loaded more than 1000 casks at 25 different sites in Germany.
This paper will discuss the experience gained during the first decade of using dry cask storage technology.
2) CONTINGENCY OPTIONS FOR THE DRY STORAGE OF MAGNOX SPENT FUEL IN THE UK - 16330
Jenny E. Morris, Galson Sciences Limited (UK); Stephen Wickham, Phil Richardson, Galson Sciences Ltd. (UK);
Colin Rhodes, NDA (UK); Mike Newland, UKAEA (UK)
<strong>The</strong> UK Nuclear Decommissioning Authority (NDA) is responsible for safe and secure management of spent nuclear fuel.
Magnox fuel is held at some Magnox reactor sites and at Sellafield where it is reprocessed using a number of facilities. It is intended
that all Magnox fuel will be reprocessed as described in the published Magnox Operating Programme (MOP). In the event, however,
that a failure occurs within the reprocessing plant, the NDA has initiated a programme of activities to explore alternative contingency
options for the management of wetted Magnox spent fuel.
Magnox fuel comprises metallic uranium bar clad in a magnesium alloy, both of which corrode if exposed to oxygen or water.
Consequently, contingency options are required to consider how best to manage the issues associated with the reactivity of the metals.
Questions such as whether Magnox spent fuel needs to be dried, how it might be conditioned, how it might be packaged and
held in temporary storage until a disposal facility becomes available, all require attention.
During storage in the presence of water, the corrosion of Magnox fuel produces hydrogen (H2) gas, which requires careful
management. When uranium reacts with hydrogen in a reducing environment, the formation of uranium hydride (UH3) may occur,
which under some circumstances can be pyrophoric, and might create hazards which may affect subsequent retrieval and/or repackaging
(e.g. for disposal). Other factors that may affect the choice of a viable contingency option include criticality safety, environmental
impacts, security and Safeguards and economic considerations.
3) WIPP: A PERSPECTIVE FROM TEN YEARS OF OPERATING SUCCESS - 16189
Phillip C. Gregory, Washington TRU Solutions (USA)
<strong>The</strong> Waste Isolation Pilot Plant (WIPP) located 35 miles east of Carlsbad, New Mexico, USA is the first and, to the author’s
knowledge, only facility if the world for the permanent disposal of defense related transuranic (TRU) waste. Soon after plutonium
was first synthesized in 1940 by a team of scientists at the University of California’s Berkley Laboratory the need to find a permanent
repository for plutonium contaminated waste was recognized due to the 24,100 year half-life of Plutonium-239. In 1957 the
National Academy of Sciences published a report recommending deep geological burial in bedded salt as a possible solution. However,
more than 50 years passed before the solution was realized when in 1999 WIPP received the first shipment of TRU waste from
the Los Alamos National Laboratory. Ten years later, more than 6,000 shipments of TRU waste have been disposed of in rooms
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Abstracts Session 41
mined in an ancient salt bed more than 2,000 feet underground. This paper provides a brief history of WIPP with an overview of
both the technical and political hurdles that had to be overcome before the idea of a permanent disposal facility became reality. <strong>The</strong>
paper focuses primarily on the safe uneventful transportation program that has move 100,000-plus containers of TRU waste from
various US Department of Energy generator and/or storage sites across the United States to southeastern New Mexico.
4) RESEARCH REACTOR SPENT NUCLEAR FUEL SHIPMENT FROM THE CZECH REPUBLIC
TO THE RUSSIAN FEDERATION - 16195
Frantisek Svitak, Karel Svoboda, Josef Podlaha, Nuclear Research Institute Rez plc. (Czech Republic)
In May 2004, the Global Threat Reduction Initiative agreement was signed by the governments of the United States and the
Russian Federation. <strong>The</strong> goal of this initiative is to minimize, in cooperation with the <strong>International</strong> Atomic Energy Agency (IAEA)
in Vienna, the existing threat of misuse of nuclear and radioactive materials for terrorist purposes, particularly highly enriched uranium
(HEU), fresh and spent nuclear fuel (SNF), and plutonium, which have been stored in a number of countries. Within the
framework of the initiative, HEU materials and SNF from research reactors of Russian origin will be transported back to the Russian
Federation for reprocessing/liquidation.
<strong>The</strong> program is designated as the Russian Research Reactor Fuel Return (RRRFR) Program and is similar to the U.S. Foreign
Research Reactor Spent Nuclear Fuel Acceptance Program, which is underway for nuclear materials of United States origin. <strong>The</strong>se
RRRFR activities are carried out under the responsibilities of the respective ministries (i.e., U.S. Department of Energy (DOE) and
Russian Federation Rosatom).
<strong>The</strong> Czech Republic and the Nuclear Research Institute Rez, plc (NRI) joined Global Threat Reduction Initiative in 2004. During
NRIs more than 50 years of existence, radioactive and nuclear materials had accumulated and had been safely stored on its
grounds. In 1995, the Czech regulatory body, State Office for Nuclear Safety (SONS), instructed NRI that all ecological burdens
from its past activities must be addressed and that the SNF from the research reactor LVR-15 had to be transported for reprocessing.
At the end of November 2007, all these activities culminated with the unique shipment to the Russian Federation of 527 fuel
assemblies of SNF type EK-10 (enrichment 10% U235) and IRT-M (enrichment 36% and 80% U235) and 657 irradiated fuel rods
of EK-10 fuel, which were used in LVR-15 reactor.
5) THERMAL SAFETY ANALYSIS OF A DRY STORAGE CASK FOR THE
KOREAN STANDARD SPENT FUEL - 16159
Jeong-Hun Cha, B. S. Youn, S. N. Kim, Kyunghee University (Korea);
K. W. Choi, Korea Institute of Nuclear Safety (Korea)
A conceptual dry storage facility, which is based on a commercial dry storage facility, was designed for the Korea standard
spent nuclear fuel (SNF) and preliminary thermal safety analysis was performed in this study. To perform the preliminary thermal
analysis, a thermal analysis method was proposed. <strong>The</strong> thermal analysis method consists of 2 parts. By using the method, the surface
temperature of the storage canister corresponding to the SNF clad temperature was calculated and the adequate air duct area
was decided using the calculation result. <strong>The</strong> initial temperature of the facility was calculated and the fire condition and half air
duct blockage were analyzed.
6) CONTINGENCY OPTIONS FOR THE DRYING, CONDITIONING AND PACKAGING
OF MAGNOX SPENT FUEL IN THE UK - 16331
Jenny E. Morris, Phil Richardson, Stephen Wickham, Galson Sciences Ltd. (UK);
Colin Rhodes, NDA (UK); Mike Newland, UKAEA (UK)
<strong>The</strong> UK Nuclear Decommissioning Authority (NDA) is responsible for safe and secure management of spent nuclear fuel.
Magnox spent fuel is held at some Magnox reactor sites and at Sellafield where it is reprocessed using a number of facilities. It is
intended that all Magnox fuel will be reprocessed, as described in the published Magnox Operating Plan (MOP). In the event, however,
that a failure occurs within the reprocessing plant, the NDA has initiated a programme of activities to explore alternative contingency
options for the management of wetted Magnox spent fuel.
Magnox fuel comprises metallic uranium bar clad in a magnesium alloy, both of which corrode if exposed to oxygen or water.
Consequently, contingency options are required to consider how best to manage the issues associated with the reactivity of the metals.
Questions of whether Magnox spent fuel needs to be dried, how it might be conditioned, how it might be packaged, and held
in temporary storage until a disposal facility becomes available, all require attention. A review of potential contingency options for
Magnox fuel was conducted by Galson Sciences Ltd, UKAEA and the NDA.
During storage in the presence of water, the corrosion of Magnox fuel produces hydrogen (H2) gas, which requires careful
management. When uranium reacts with hydrogen in a reducing environment, the formation of uranium hydride (UH3) may occur,
which under some circumstances can be pyrophoric, and might create hazards which may affect subsequent retrieval and/or repackaging
(e.g. for disposal). Other factors that may affect the choice of a viable contingency option include criticality safety, environmental
impacts, security and Safeguards and economic considerations.
7) NUCLEAR SAFETY AT THE HEART OF THE DESIGN OF THE NEW SELLAFIELD
PRODUCT AND RESIDUE STORE - 16077
Alec Glover, Sellafield Limited (UK)
A new facility for the storage of multi tonne quantities of fissile material has been constructed in the UK on the NDA owned
Sellafield Site: <strong>The</strong> Sellafield Product & Residue Store(SPRS) will cost £260M to construct and enter active operations in early
2011. <strong>The</strong> asset will serve to provide safe, secure storage facilities over a design life of at least fifty years.
<strong>The</strong> author will present a technical presentation which describes the following:
• <strong>The</strong> context of the SPRS facility in UK Government strategy for the longer term management and storage of product and
residues.
• <strong>The</strong> hazards and key stakeholder constraints impacting upon the facility.
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Session 41-42 Abstracts
• Work undertaken taken to decide upon the overall form and configuration of the building.
• Insight into the design of the passive cooling system.
• Work undertaken to ensure that Nuclear Safety is an integral factor in the design and construction of the facility.
• Overall project status.
In concluding, the author will outline some of his key learning points from his period of eight years as manager of the design
of the SPRS facility.
8) ENGINEERING CHALLENGES IN THE MECHANICAL DESIGN OF A NEW SHIELDED
SHIPPING CASK FOR VITRIFIED WASTE PRODUCTS - 16256
R.K. Gupta, S.P. Patil, D.S Sandhanshive, A.K. Singh, K.M. Singh, Bhabha Atomic Research Centre (India)
VWP shipping casks are designed, built, and maintained to ensure utmost safety and conformance to regulatory requirements,
essential for handling and transport in public domain. This is achieved by proper sizing for static and dynamic stability, detailed
quality surveillance during manufacture, physical testing of models for design validation and selection of prime movers for transfer.
Actual transport is planned carefully with due cognizance to the logistics of handling and interim storage in specially engineered
cooling vaults for several decades prior to final disposal.
<strong>The</strong> closed fuel cycle adopted in our Nuclear Programme is extremely sensitive to safety and regulatory issues. But while Vitrified
Waste Packages are produced in Trombay, Tarapur and Kalpakkam, the interim storage site with engineered cooling under
surveillance is available only in Tarapur. Thus, cross country road transport of VWP Casks from Trombay (130 Kilometers) and
Kalpakkam (1200 kilometers) need careful site-specific considerations and mandatory compliance with safety guidelines.
Five years ago, such a transport cask was designed and built for Trombay plant which, at that time, produced vitrified waste
packages with activity limited to 25000 curies per canister. While the cask is still being used for shipment of VWP from Trombay
to Tarapur, the plant now requires a new cask for shipping packages for fresh batches of HLW having radioactivity levels close to
250,000 curies per canister. This paper describes the design challenges associated with the restrictions of using existing handling
facilities for loading and transporting. Authors realize that all aspects of an acceptable final design require extensive involvement
of experts from several disciplines. No single agency can do this work in isolation. But the contents of this paper are limited to
describing critical design issues from the mechanical engineers point of view. Changes made in the old design have been brought
out in respect of fabrication, physical testing, modifications of existing inter-facility-transfers at Trombay and unloading and handling
at Tarapur. One additional design consideration is horizontal mounting of the new cask on transport trailer as against the vertical
mounting currently in practice. Needless to say, design considerations adopted in the previous instance would also be touched
upon, albeit briefly. <strong>The</strong> authors have assumed that data made available to them on package size, weight, shielding and regulatory
SESSION 42 - ER SITE CHARACTERIZATION AND MONITORING - PART 2 OF 2
1) RADIOLOGICAL CHARACTERIZATION OF A COPPER/COBALT MINING & MILLING SITE - 16322
Matthew Arno, Janine Arno, Foxfire Scientific (USA); Donald Halter, Foxfire Scientific, Inc. (USA);
Robert Berry, Foxfire Scientific, Inc.(UK); Stephen Gilliland, Noel Hamilton, Foxfire Scientific (USA);
Ian Hamilton, Foxfire Scientific, Inc. (USA)
Extensive copper and cobalt ore deposits can be found in the Katanga Province of the Democratic Republic of the Congo near
the city of Kolwezi. <strong>The</strong>se deposits have been mined extensively via open pit and underground mines since the 19th century, with
many changes in control of the mines; including colonial industrial control and Congolese government control. With the recent reestablishment
of a relatively stable democratic government in the DRC, foreign investors are returning to the area to restart mining
activities that were abruptly terminated in the 1990s due to political turmoil. <strong>The</strong>se new projects are being performed in accordance
with World Bank and <strong>International</strong> Finance Corporation Social & Environmental Sustainability standards. As part of these standards,
radiological characterization of the mines, processing facilities, and surrounding environment was conducted to establish current
conditions, evaluate human health and ecological risks, and provide a basis for establishment of radiation safety and environmental
remediation programs. In addition to Naturally Occurring Radioactive Materials associated with the copper and cobalt ore,
the site was reputedly historically used to store ore from the Shinkolobwe uranium mine, the source of the uranium ore for the Manhattan
project.
<strong>The</strong> radiological characterization was conducted via extensive gamma radiation surveys using vehicle-mounted sodium-iodide
detectors, random grid composite soil sampling, biased soil sampling of areas with elevated gamma radiation levels, and sampling
of surface water features. <strong>The</strong> characterization revealed broad areas of elevated gamma radiation levels of up to 160 µGy/hr in two
distinct areas believed to be the Shinkolobwe uranium mine ore storage locations. Other areas, with gamma radiation levels of up
to 80 µGy/hr, were detected associated with ore refining tailings and waste rock (overburden) sediments.
2) RADIOACTIVITY IN SURFACE AND GROUNDWATER NEAR OLD RADIUM AND URANIUM MINES IN
PORTUGAL - 16258
Fernando P. Carvalho, Instituto Tecnológico e Nuclear(Portugal);
João M. Oliveira, Magarida Malta, Nuclear and Technological Institute (Portugal)
Concerns with the potential radiological hazards posed by the uranium mining and milling wastes have been the rational for
radioactivity measurements in surface and groundwater of the Centre-North region of Portugal. Water samples collected in former
uranium mines, in streams, in irrigation wells, and in drinking water supplies to villages of this region were analyzed for uranium
series radionuclides by radiochemistry and alpha spectrometry. For example, water from the Bica Mine (Sabugal), contained 4.4
Bq L-1 , 1.5 Bq L-1 , and 0.48 Bq L-1 of dissolved 238U, 226Ra and 210Po, respectively, and these were the highest concentrations
measured in waters from the region. Water samples from mines where no sulfuric acid was used for in situ uranium leaching were
under 150 mBq L-1 of 238U and 226Ra and even less for other dissolved radionuclides. Water from irrigation wells in the region
generally displayed concentrations under 50 mBq L-1 both for 238U and for 226Ra, but several wells near the Bica Mine displayed
enhanced concentrations of dissolved uranium, reaching 820 mBq L-1 of 238U. Drinking water from public water supplies in the
villages and towns of this region contained 238U, 226Ra, 230Th, 210Po and 232Th generally below 50 mBq L-1 each, and total alpha
114

Abstracts Session 43
radioactivity was generally less than 0.5 Bq L -1 as recommended for drinking water. Only one water supply from a local spring to
a village exceeded the recommended limit for alpha radioactivity in drinking water with 1.12 Bq L -1 . <strong>The</strong> overall assessment of
water radioactivity in this uranium mining region indicated that water resources were not significantly contaminated by the historic
radium and uranium mining. Nevertheless, acid mine waters from Urgeiriça and Bica mines still require treatment to prevent dispersal
of the acid and radionuclides into the aquifer.
SESSION 43 - URANIUM MINING AND MILLING SITES ER
1) DESIGN IMPROVEMENTS AND ALARA AT U.S. URANIUM IN SITU RECOVERY FACILITIES - 16415
Steven Brown, SENES (USA)
In the last few years, there has been a significant increase in the demand for Uranium as historical inventories have been consumed
and new reactor orders are being placed. Numerous mineralized properties around the world are being evaluated for Uranium
recovery and new mining / milling projects are being evaluated and developed . Ore bodies which are considered uneconomical
to mine by conventional methods such as tunneling or open pits, can be candidates for non-conventional recovery techniques,
involving considerably less capital expenditure. Technologies such as Uranium In Situ Leaching / In Situ Recovery (ISL / ISR -
also referred to as solution mining), have enabled commercial scale mining and milling of relatively small ore pockets of lower
grade, and are expected to make a significant contribution to overall world wide uranium supplies over the next ten years. Commercial
size solution mining production facilities have operated in the US since the mid 1970s.
However, current designs are expected to result in less radiological wastes and emissions relative to these first generation plants
(which were designed, constructed and operated through the 1980s). <strong>The</strong>se early designs typically used alkaline leach chemistries
in situ including use of ammonium carbonate which resulted in groundwater restoration challenges, open to air recovery vessels
and high temperature calcining systems for final product drying vs the zero emmisionsvaccum dryers as typically used today.
Improved containment, automation and instrumentation control and use of vacuum dryers in the design of current generation plants
are expected to reduce production of secondary waste byproduct material, reduce Radon emisions and reduce potential for employee
exposure to uranium concentrate aerosols at the back end of the milling process.
2) RADIONUCLIDE TRANSFER FROM URANIUM MINE WATER TREATMENT PONDS TO VEGETATION - 16260
Fernando P. Carvalho, Instituto Tecnológico e Nuclear (Portugal);
João M. Oliveira, Magarida Malta, Nuclear and Technological Institute (Portugal)
Sulphuric acid was used in large amounts for in situ leaching and static leaching of uranium ore in uranium mines at Portugal.
<strong>The</strong> production of uranium ceased years ago and at several mines water treatment plants still are in operation to neutralize pH of
acid mine waters and to remove radioactivity before releasing treated water into surface water streams. Sludge from water treatment
is decanted and deposited in ponds which, as wet areas, develop spontaneous vegetation and attract biota such as insects and
birds. Distribution of uranium series radionuclides in these ponds was investigated in the mud, overlaying water, and spontaneous
vegetation. Radionuclide concentrations in the sludge reach about 41 000 Bq kg-1 for 238U, 1 700 Bq kg-1 for 226Ra, and 1 200 Bq
kg-1 for 210 Bq. This paper reports on the bioavailability of radionuclides from the sludge to spontaneous vegetation growing in the
ponds area, such as grass, rush and reeds, and discusses potential transfer of these radionuclides into the food chain.
3) COMPLETION OF THE SOUTH ALLIGATOR VALLEY REMEDIATION, NORTHERN TERRITORY,
AUSTRALIA - 16198
Peter Waggitt, IAEA (Austria); Mike Fawcett, Fawcett Minesite Rehabilitation Services (Australia)
13 uranium mines operated in the South Alligator Valley of Australias Northern Territory between 1953 and 1963. At the end
of operations the mines, and associated infrastructure, were simply abandoned. As this activity preceded environmental legislation
by about 15 years there was no remediation.
In the 1980s it was decided that the whole area should become an extension of the adjacent World Heritage, Kakadu National
Park. As a result the Commonwealth Government made an inventory of the abandoned mines and associated facilities in 1986. This
established the size and scope of the liability and formed the framework for a possible future remediation project. <strong>The</strong> initial program
for the reduction of physical and radiological hazards at each of the identified sites was formulated in 1989 and the works
took place from 1990 to 1992. But even at this time, as throughout much of the valleys history, little attention was being paid to
the long term hopes and plans of the traditional land owners.
<strong>The</strong> Aboriginal Traditional Owners, the Gunlom Land Trust, were granted freehold Native Title to the area in 1996. <strong>The</strong>y
immediately leased the land back to the Commonwealth Government so it would remain a part of Kakadu National Park, but under
joint management. One condition of the lease required that all evidence of former mining activity be remediated by 2015.
<strong>The</strong> consultation, and subsequent planning processes, for a final remediation program began in 1997. A plan was agreed in
2004 and, after funding was granted in 2005, works implementation commenced in 2007. An earlier paper described the planning
and consultation stages, experience involving the cleaning up of remnant uranium mill tailings and other mining residues; and the
successful implementation of the initial remediation works. This paper deals with the final planning and design processes to complete
the remediation works, which is due in 2009. <strong>The</strong> issues of final containment design and long term stewardship are addressed
in the paper as well as some comments on lessons learned through the life of the project.
4) GUNNAR URANIUM MINE ENVIRONMENTAL REMEDIATION - NORTHERN SASKATCHEWAN - 16102
Joseph Muldoon, Laurier Schramm, Saskatchewan Research Council (Canada)
Thirty-six now-abandoned uranium mine and mill sites were developed and operated in Northern Saskatchewan, Canada, from
approximately 1957 through 1964. During their operating lifetimes these mines produced large quantities of ore and tailings. <strong>The</strong>
Gunnar Mine is located on the shores of Lake Athabasca, the 22nd largest lake in the world. <strong>The</strong> Gunnar mine (open pit and underground)
produced over 5 million tonnes of uranium ore and nearly 4.4 million tonnes of mine tailings. <strong>The</strong>re is an estimated
2,710,700 m3 of waste rock that abuts the shores of Lake Athabasca. After closure in the 1960‘s, the Gunnar site along with all of
the other uranium mine and mill sites were abandoned with little remediation and no reclamation being done. <strong>The</strong> governments of
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Session 43-45 Abstracts
Canada and Saskatchewan are now funding the clean-up of these abandoned northern uranium mine and mill sites and have contracted
the management of the project to the Saskatchewan Research Council. <strong>The</strong> clean-up activity is expected to take about 8
years, followed by 10-15 years of monitoring activity before the sites are to be released into an institutional controls program that
will allow government oversight of a long term management and monitoring program. <strong>The</strong> Gunnar site, because of the magnitude
of tailings and waste rock, is subject to an environmental site assessment process regulated by both provincial and federal governments.
This process requires a detailed study of the projected environmental impacts resulting from the mining activities and an
analysis of projected impacts from remediation efforts. Prescribed environmental and land use endpoints will be made based on the
environmental assessment studies and remediation options analyzed and implemented based on expected results. Remediation
options range from deep lake disposal of tailings to disposal of tailings in the open pit which is now filled with water and fish (contaminated,
but which are reproducing successfully) to covering the tailings with a cap.
5) SUSTAINABLE COVERS FOR URANIUM MILL TAILINGS, USA: ALTERNATIVE
DESIGN, PERFORMANCE, AND RENOVATION - 16369
William J. Waugh, S.M. Stoller Corporation (USA); Craig H. Benson, University of Wisconsin-Madison (USA);
William H. Albright, Desert Research Institute (USA)
<strong>The</strong> U.S. Department of Energy Office of Legacy Management is investigating alternatives to conventional cover designs for
uranium mill tailings. A cover constructed in 2000 near Monticello, Utah, USA, was a redundant design with a conventional lowconductivity
composite cover overlain with an alternative cover designed to mimic the natural soil water balance as measured in
nearby undisturbed native soils and vegetation. To limit percolation, the alternative cover design relies on a 160-cm layer of sandy
clay loam soil overlying a 40-cm sand capillary barrier for water storage, and a planting of native sagebrush steppe vegetation to
seasonally release soil water through evapotranspiration (ET). Water balance monitoring within a 3.0-ha drainage lysimeter, embedded
in the cover during construction, provided convincing evidence that the cover has performed well over a 9-year period
(20002009). <strong>The</strong> total cumulative percolation, 4.8 mm (approximately 0.5 mm yr-1), satisfied a regulatory goal of

Abstracts Session 45
testing and optimization phases of the particle detection system which was created to simulate an overland survey environment as
realistically as possible. MACTEC was able to successfully demonstrate the capabilities of the system by not only meeting the identified
specifications, but by beating the clients specifications while saving significant costs that would be incurred with a full-scale
test deployment methodology.
C) INDEPENDENT MONITORING OF RADIOLOGICAL IMPACT AT DECOMMISSIONED NPP A1 SITE - 16074
Ondrej Slavik, Martin Listjak, Alojz Slaninka, Jozef Moravek (SlovaKia); Frantisek Soos, JAVYS, a.s. (Slovakia); Sylvia
Dulanska, Comenius University (Slovakia)
Monitoring of characteristics of the radiation situation in close surrounding of the decommissioned NPP A1 by an independent
organization is described and discussed in the paper. <strong>The</strong> measurements are carried out in the NPP A1 site close to the VUJE
operation building, not far from the places, where the decommissioning activities are concentrated. <strong>The</strong>se activities relate to bringing
the NPP A1 to safer conditions, e.g. cleanup of contaminated underground waste water reservoirs, solidification of the removed
sludge from these reservoirs by an in situ open air solidification system, cleaning of contaminated concretes and so on. Other activities
also relate to radiological impact to the environment, e.g. radioactive waste processing at Bohunice RW-Treatment Centre and
intensive traffic of sources of ionising radiation to and from this centre located very close to the place mentioned above. Results of
the measurements carried out by VUJE accredited laboratory in the frame of Decommissioning project of NPP A1 present an uninterrupted
time series of measurements and enable evaluation of development for the last 17 years. <strong>The</strong> monitoring results demonstrate
that the only significant radionuclide indicating radiological impact of the decommissioning is 137Cs. Its activity concentration
in atmospheric aerosols at the sampling point has been time to time elevated and in average is by about one order higher in
comparison with a 100 km far reference (background) site.
D) EXPERIENCE OF THE INTERNATIONAL COOPERATION UNDER THE RUSSIAN-AMERICAN
AGREEMENT ON REPATRIATION HEU SNF OF RESEARCH REACTORS (EXPORT FROM
BULGARIA, LATVIA, HUNGARY, ETC. THE COUNTRIES) - 16172
Borovitskiy Stepan, FSUE FCNRS (Russia)
Keystone of the Russian Federation policy concerning the SNF management is based upon the fuel reprocessing principle that
provides ecology friendly management of fission products and recycling of nuclear materials.
<strong>The</strong> strategic areas in SNF management are:
• establishment of a reliable system for long-term monitored SNF storage;
• development of SNF reprocessing technologies ;
• balanced involvement of the recycled nuclear materials in the nuclear fuel cycle;
• final isolation (disposal) of RW resulted from SNF reprocessing.
<strong>The</strong> prime purpose of SNF management Concept is to develop the strategy for SNF management in Russian Federation up to
2020 and for the future up to 2030 and to select key structural and technical approaches and effective mechanisms assuring the Concept
implementation.
To implement the Concept is to establish a State Unified System for SNF management, comprising all required legal, regulatory,
structural and financial mechanisms, as well as human resources and facilities.
<strong>The</strong> top priority at all stages of SNF management is to provide nuclear, radiation and ecological safety, physical protection and
control of fissile materials and not to impose excessive burden on future generations.
E) PLAN FOR SITE RELEASE OF DECOMMISSIONING PROJECT OF KRR-1&2 - 16287
Sang Bum Hong, Korea Atomic Energy Research Institute (Korea)
Its important to release criteria and survey procedures for site release from regulatory control in the decommissioning projects.
<strong>The</strong> objective of the plan for site cleanup should be considering the optimization a radiological protection of the public and environment.
In this study, the plan for site release was established the release criteria and survey design of the site and building of
KRR-1&2. <strong>The</strong> decommissioning project of KRR-1&2 was launched in January 1997. <strong>The</strong> work scopes during the reactor decommissioning
project are the dismantling of all the facilities and the removal of all the radioactive materials from the reactor site. After
confirming the removal of the radioactive material, the site and buildings will be returned to the Korea Electric Power Company
(KEPCO).
Some of the countries already developed and applied the release criteria, but the criteria has not establish in Korea. <strong>The</strong> release
criteria for site and building were set up by considering the final purpose of site and comparing the dose criteria used in Germany
and USA. Based on these result, the site specific release levels was calculated for the KRR site and building by using RESRAD
and RESRAD-Build codes.
<strong>The</strong> survey design was carried out by using the MARSSIM, the site and building could be classified by class 2 or class 3 based
on the decontamination results and potential contamination. <strong>The</strong> site and building were divided and calculated the number of sample
in each survey unit. Based on the survey design, the dose rate, in situ gamma spectrometry was measured using survey meter
connected with GPS systems on the surface soil of the site.
F) PRESENT STATE OF REMEDIATION OF MECSEK URANIUM MINES, RADIOACTIVE PARAMETERS - 16337
András Várhegyi, MECSEK-ÖKO Environment Co. (Hungary);
Zorán Gorjánácz, MECSEKÉRC Environment Co. (Hungary); János Somlai, Pannon University (Hungary)
In the period of 19561997 Uranium ore mining and chemical ore processing activity had taken place in Mecsek Mountains,
SW Hungary. After closing the mines, a huge environment remediation project started at the affected area what is almost completed
by 2009; only sporadic soil contaminations are re-mained. <strong>The</strong> results of radiological monitoring satisfactorily indicated the
decrease of radiation levels, both on the work-places and in the close living sites. <strong>The</strong> original radiation back-ground was gradually
reconstructed while all the waste rock piles and tailings ponds were covered. During the field works, the population of the most
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Session 46-48 Abstracts
affected village, Pellérd suffered about 1 mSv extra annual dose due to the emission of tailings ponds. Decrease of occupational
dose was also indicated on the tailings pond workplaces: the earlier measured 56 mSv/year (without cover) decreased to the satisfactory
11.5 mSv/year value as covering of the highly radioactive surface progressed. <strong>The</strong> decisive component of excess dose is the
short living radioactivity (radon daughters) in air.
SESSION 46 - PANEL: UK NDA AND TIER 1 FUNDING, CONTRACTING,
SUBCONTRACTING SELECTION AND ARRANGEMENTS
ABSTRACTS NOT REQUIRED
SESSION 47 - PANEL: UMREG PANEL/ROUNDTABLE
ABSTRACTS NOT REQUIRED
SESSION 48 - LIQUID WASTE TREATMENT PROCESS AND EXPERIENCE
1) U.S. DEPARTMENT OF ENERGY’S - 16037
Dennis Kelley, Pacific Nuclear Solutions (USA); Yury Pokhitonov, V.G. Khlopin Radium Institute(Russia)
Large amounts of liquid radioactive waste have existed in the U.S. and Russia since the 1950’s as a result of the Cold War.
Comprehensive action to treat and dispose of waste products has been lacking due to insufficient funding, ineffective technologies
or no proven technologies, low priority by governments among others. Today the U.S. and Russian governments seek new, more
reliable methods to treat liquid waste, in particular the legacy waste streams. A primary objective of waste generators and regulators
is to find economical and proven technologies that can provide long-term stability for repository storage.
In 2001, the V.G. Khlopin Radium Institute (Khlopin), St. Petersburg, Russia, and Pacific Nuclear Solutions (PNS), Indianapolis,
Indiana, began extensive research and test programs to determine the validity of polymer technology for the absorption and
immobilization of standard and complex waste streams. Over 60 liquid compositions have been tested including extensive irradiation
tests to verify polymer stability and possible degradation. With conclusive scientific evidence of the polymers effectiveness in
treating liquid waste, both parties have decided to enter the Russian market and offer the solidification technology to nuclear sites
for waste treatment and disposal.
In conjunction with these efforts, the U.S. Department of Energy (DOE) will join Khlopin and PNS to explore opportunities
for direct application of the polymers at predetermined sites and to conduct research for new product development. Under DOEs
Initiatives for Proliferation Prevention(IPP) program, funding will be provided to the Russian participants over a three year period
to implement the program plan.
This paper will present updated details of U.S. DOEs IPP program, the project structure and its objectives both short and longterm,
polymer tests and plications for LLW, ILW and HLW, and new product development initiatives.
2) OPERATIONAL EXPERIENCE WITH A COMMERCIAL PLANT FOR STABILISATION OF RADIOACTIVE
SLUDGE AND OTHER MATERIALS IN THE UNITED KINGDOM - 16042
Madoc Hagan, Rowland Cornell, Brian Riley, Nuvia Limited (UK);
Bryan Ware, UK Kingdom Atomic Energy Authority(UK)
In 2000, Nuvia Limited was contracted to design, build and commission a waste treatment plant (WETP) to stabilise the active
sludge stored in the External Active Storage Tanks (EAST) at UKAEA Winfrith, UK. <strong>The</strong> sludge was generated during the operational
period of the prototype Steam Generating Heavy Water Reactor (SGHWR), which is now in the process of being decommissioned.
This work supports UKAEA’s mission, which is to carry out environmental restoration of its nuclear sites and to put them
to alternative uses wherever possible. Recently UKAEA has been reorganised and responsibility for the site lies with Research Sites
Restoration Limited (RSRL) with funding provided by the Nuclear Decommissioning Authority (NDA).
<strong>The</strong> process of stabilisation of the SGHWR sludge from the EAST tanks within 500 litre stainless steel drums in the Winfrith
EAST Treatment Plant (WETP) using ordinary Portland cement (OPC) and blast furnace slag (BFS) is now almost complete. At
this stage it was planned to decommission and demolish the WETP facilities but RSRL have introduced a further stabilisation project
involving thorium metal waste ahead of the start of the planned decommissioning. As a result, the facilities are to be revised to
provide for the encapsulation of bars of thorium metal within modified 500 litre drums together with a number of necessary changes
to the plant control system.
3) THE DEVELOPMENT OF A METHOD FOR THE SIMULTANEOUS MEASUREMENT OF CERIUM (IV) AND
CHROMIUM (VI) SPECIES IN NITRIC ACID MEDIA - 16124
Ian D Nickson, John Tyndall Institute for Nuclear Research (UK); Colin Boxall, Lancaster University (UK);
Angela Jackson, Guy O.H. Whillock, National Nuclear Laboratory(UK)
<strong>The</strong> corrosion of stainless steel in nitric acid media is a major concern for the nuclear industry. Several reprocessing schemes
such as PUREX (Plutonium Uranium Reduction Extraction) and UREX (Uranium Reduction Extraction) utilise nitric acid media,
and an understanding of the behaviour of key chemical species in these process streams is vital if their effect on associated corrosion
reactions and their rates is to be accurately assessed and quantified. This will allow for more accurate prediction of the working
lifetime of any stainless steel surface in contact with the process stream in question.
Two such key species that are found in nuclear process streams are cerium as Ce (IV) and chromium as Cr(VI), both of which
may act as corrosion accelerants. <strong>The</strong> redox chemistry of cerium and chromium in highly active liquor (HAL) will depend on
nitrous acid concentration, temperature, acidity, total nitrate and possibly the influence of other dissolved species and hence an analytical
technique for the on-line measurement of these quantities would be useful for lifetime prediction and corrosion prevention.
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As a result of this, a strategy for the simultaneous measurement of both Ce(IV) and Cr(VI) species in the presence of other ions
typically found in process streams (such as Iron, Magnesium Neodymium and Aluminium) has been developed. <strong>The</strong> work presented
will discuss the design and implementation of the electrochemical techniques that we have used in the development of this strategy
and in the measurement of the species in question.
4) TREATMENT OF LIQUID RAW - TRIAL OPERATION OF FINAL TREATMENT CENTER MOCHOVCE - 16178
Tibor Krajc, Milan Zatkulak, Marian Stubna, VUJE, a.s. (Slovakia); Vladimir Remias, JAVYS, a.s., (Slovaki)
<strong>The</strong> Final Treatment Center (FTC) at Mochovce Nuclear Power Plant (NPP) has been introduced to trial operation in 10/2007.
One-year trial operation of facility was planned. <strong>The</strong> Center is designed for treatment of liquid operational RAW and the treatment
of radioactive wastes originated from decommissioning of NPP A-1 in Jaslovské Bohunice is tested, too.
<strong>The</strong> Center and processes parameters are described and a short description of bituminisation and cementation technologies
implemented to FTC including the auxiliary processes is given as well.
<strong>The</strong> time schedule of start-up and trial operation phases is described and discussed. <strong>The</strong> amounts of treated wastes, the production
of waste packages and the balance of raw materials and energy consumption are displayed too.
<strong>The</strong> evaluation of experience gained in the phase of Center trial operation for bituminisation processes (film evaporator process
and the bituminisation of resins) and the cement grouting is a part of this paper.
<strong>The</strong> identification of key interdependences within process parameters and treatment product properties and the fulfillment of
the projected output parameters and required qualitative parameters of individual treated RAW products are displayed.
5) RADIOACTIVE OIL DECONTAMINATION DEVELOPMENT — AN OVERVIEW - 16251
John Krasznai, Kinectrics Inc. (Canada)
Insulating, hydraulic and vacuum pump oils are used extensively in CANDU plants. It is inevitable that at some point in the
equipment life cycle that these oils will become waste products and their disposal needs to be properly managed. <strong>The</strong> presence of
radioactivity and conventional contamination in the oils (mixed waste) pose special challenges to the waste manager.
This paper provides an overview of waste oil streams that have been problematic in the CANDU nuclear industry and the
decontamination processes that were developed for each to effectively remove a variety of radioactive species including tritium as
well as conventional hazardous materials such as PCB, lead and cadmium.
6) INCINERATION OF CONTAMINATED OIL FROM SELLAFIELD - 16246
Craig Broadbent, Studsvik UK Limited (UK); Helen Cassidy, Sellafield Limited (UK);
Anders Stenmark, Studsvik Nuclear AB (Sweden)
Studsvik have been incinerating Low Level Waste (LLW) at its licensed facility in Sweden since the mid-1970s. This process
not only enables the volume of waste to be significantly reduced but also produces an inert residue suitable for final disposal. <strong>The</strong>
facility has historically incinerated only solid dry LLW, however in 2008 an authorisation was obtained to permit the routine incineration
of LLW contaminated oil at the facility.
Prior to obtaining the authorisation to incinerate oils and other organic liquids - both from clean-up activities on the Studsvik
site and on a commercial basis - a development program was established. <strong>The</strong> primary aims of this were to identify the optimum
process set-up for the incinerator and also to demonstrate to the regulating authorities that the appropriate environmental and radiological
parameters would be maintained throughout the new process.
<strong>The</strong> final phase of the development program was to incinerate a larger campaign of contaminated oil from the nuclear industry.
A suitable accumulation of oil was identified on the Sellafield site in Cumbria and a commercial contract was established to
incinerate approximately 40 tonnes of oil from the site. <strong>The</strong> inventory of oil chosen for the trial incineration represented a significant
challenge to the incineration facility as much of it had degraded following years of storage and was from various sources onsite.
In order to transport the contaminated oil from the Sellafield site in the UK to the Studsvik facility in Sweden several challenges
had to be overcome. <strong>The</strong>se included characterisation, packaging and international transportation (under a Transfrontier Shipment
(TFS) authorisation) for one of the first transports of liquid radioactive wastes outside the UK.
<strong>The</strong> incineration commenced in late 2007 and was successfully completed in early 2008. <strong>The</strong> total volume reduction achieved
was greater than 97%, with the resultant ash packaged and returned to the UK (for ultimate disposal at the UK LLWR) in November
2008.
<strong>The</strong> paper will provide additional information on the characterisation, packaging and incineration process as well as describe
the national and international regulatory frameworks applicable to the project.
7) SOLIDIFICATION OF RADIOACTIVE LIQUID WASTES, TREATMENT OPTIONS
FOR SPENT RESINS AND CONCENTRATES - 16405
Andreas Roth, Hansa Projekt Anlagentechnik GmbH (Germany)
Ion exchange is one of the most common and effective treatment methods for liquid radioactive waste. However, spent ion
exchange resins are considered to be problematic waste that in many cases require special approaches and pre-conditioning during
its immobilization to meet the acceptance criteria for disposal. Because of the function that they fulfill, spent ion exchange resins
often contain high concentrations of radioactivity and pose special handling and treatment problems.
Another very common method of liquid radioactive waste treatment and water cleaning is the evaporation or diaphragm filtration.
Both treatment options offer a high volume reduction of the total volume of liquids treated but generate concentrates which
contain high concentrations of radioactivity.
Both mentioned waste streams, spent resins as well as concentrates, resulting from first step liquid radioactive waste treatment
systems have to be conditioned in a suitable manner to achieve stable waste products for final disposal.
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<strong>The</strong> most common method of treatment of such waste streams is the solidification in a solid matrix with additional inactive
material like cement, polymer etc. In the past good results have been achieved and the high concentration of radioactivity can be
reduced by adding the inactive material. On the other hand, under the environment of limited space for interim storage and the
absence of a final repository site, the built-up of additional volume has to be considered as very critical. Moreover, corrosive effects
on cemented drums during long-term interim storage at the surface have raised doubts about the long-term stability of such waste
products.
<strong>The</strong> paper will discuss alternative treatment options by means of drying and compaction in order to achieve volume reduction
and high quality waste products.
8) THE INFLUENCE OF SORPTION PROPERTIES OF THE ADMIXTURE WASTE FORM
ON THE MIGRATION OF RADIONUCLIDE FROM SALIGNY REPOSITORY - 16255
Daniela Dogaru, National Commission for Nuclear Activities Control (Romania);
Ortenzia Niculae, National Agency for Radioactive Waste (Romania); Gheorghita Jinescu, Politehnica University of
Bucharest (Romania); Octavian G. Duliu, University of Bucharest (Romania); Gheorghe Dogaru, National Institute of
Reserch & Development for Physics and Nuclear Engineering-Horia Hulubei (Romania)
<strong>The</strong> paper describes the results obtained in the laboratory investigations on the mechanical and sorption properties of the
cement-based radioactive waste form containing two kinds of sludge in different concentrations. One of them simulates the sludge
obtained by treatment of liquid radioactive effluents using an anionic polyelectrolyte named PA-type, and the other one simulates
the sludge obtained by decontamination of contaminated surfaces using a hydrogel named pNaAc- type. <strong>The</strong> influence of the concentration
of sludge on the compressive as well as on bending strength of the cement-based radioactive waste forms was studied.
<strong>The</strong> sorption properties of two radionuclides were studied.
SESSION 49 - L/ILW WASTE ANALYSIS TECHNOLOGIES - PART 3 OF 3
1) RADIOLOGICAL MONITORING SYSTEMS FOR WASTE CHARACTERISATION IN THE ENVIRONMENT OF
OUR DECOMMISSIONING SOLUTIONS - 16013
Marina Sokcic-Kostic, Roland Schultheis, NUKEM Technologies GmbH (Germany)
Decommissioning and dismantling of nuclear sites is an increasing business in Europe and worldwide. New methods and
instruments are demanded to perform it effectively and economically. NUKEM Technologies has accepted this challenge and has
shown that there is a specific solution for each task.
Nukem monitoring systems include Bridge Monitors for incoming radwaste, Sorting Monitors to separate low, intermediate
and high level waste, Drum/Container Monitors mainly for outgoing waste, Monitors for Room Clearance Measurements and High
Throughput Free Release Measurement Systems. <strong>The</strong> last monitor was designed for a 100% measurement of soil or building material
with up to 50.000 kg waste throughput per hour.
2) MGAV10: THE LATEST EVOLUTION IN THE MULTI-GROUP ANALYSIS CODE - 16248
Stephen Croft, Andrey Bosko, Canberra Industries Inc. (USA); Ray Gunnink, Consulant (USA);
Sasha Philips, Joe Lamontagne, Canberra Industries Inc. (USA); Markku Koskelo, Canberra Albuquerque Inc. (USA);
Robert McElroy, Canberra Industries Inc. (USA)
At many points in the safe and transparent handling of plutonium materials the relative isotopic composition of the principle
isotopes needs to be known. Sometimes this information may be of primary interest - such as in the verification of safeguard declarations
or in the confirmation of the reactivity of mixed oxide fuel. At other times, e.g., for radioactive waste characterization, the
isotopic composition may be needed to calculate specific thermal power or specific spontaneous fission rates for the item under
study, which can subsequently be combined with calorimetric and correlated neutron counting measurements, respectively, in order
to make quantitative assessments of the mass of Pu and associated nuclides that are present in an item.
<strong>The</strong> Multi-Group Analysis code MGA is a highly regarded and widely used computer code for the analysis of high resolution
gamma ray spectra in order to extract the relative isotopic composition of plutonium for a diversity of items with minimal prior
information. It has been honed over many years to give reliable results for a broad range of measurement scenarios commonly
encountered in the fuel cycle. <strong>The</strong> nuclear industry is not dormant however and the demands on such codes continue to shift as a
combination of technology and necessity open up new application areas. For example, while MGA had its origins in the analysis
of clean spectra on product material principally for nuclear safeguards applications taken with germanium detectors having good
low-energy resolution, it is now widely applied to the characterization of drummed waste forms and the complex spectra from such
items acquired with much larger volume and poorer resolution detectors often used in such applications for the dual use of quantitative
assay of the many gamma-emitters.
This new domain of operational experience resulted in the need to enhance MGA to deal with spectra of poor statistical quality
and also to cope with some of the complications that arise in the analysis of unusual spectra. Together with some additional
changes made to incorporate feedback since the release of version 9.63 (which had minor revisions denoted by the letters A through
H) of the code this has resulted in the creation of MGA v10.
In this paper we shall outline the main changes to the code explaining why they were conceived and implemented. We illustrate
what kinds of measurement problems can now be addressed over and above the previous capabilities which have been preserved
and verified by the same set of regression tests that have been applied to previous generation of the code.
3) USE OF A WASTE TRACKING SYSTEM AS A WASTE MANAGEMENT TOOL - 16302
Karan North, Magnox South Ltd (UK)
As the Magnox Reactor Sites transitioned from electricity generation into decommissioning, the quantity, types and generation
rate of waste changed. Most of the existing waste management systems were developed to support managing operational wastes;
not those generated from decommissioning activities. Safe handling, proper onsite management and offsite disposal of waste
requires information tracking in an integrated database that is capable of providing detailed reports.
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A novel method for management of nuclear and hazardous waste eliminates the paperwork whilst ensuring electronic integrity
of the waste data. To address the changing needs, a robust off-the-shelf Waste Tracking Software (WTS) system was procured
providing the capability to track both radiological and non-radiological decommissioning wastes generated from multiple nuclear
reactor sites. This centralised real-time tracking system tracks and reports waste related actions including operational waste management
activities such as treatment, repacking and storage activities; utilises existing waste characterisation data; provides virtual
package preparation, makes available waste related information to receiving facilities, and prepares waste consignment and transportation
documentation. <strong>The</strong> WTS also supports internal and external waste reporting needs and interfaces with other database programmes.
Simply put, it is a waste management tool to control both containerised and non-containerised wastes from point of generation
to ultimate dispositioning.
4) DESIGN AND OPERATION OF THE COMBINED TECHNOLOGY AUTOMATED
WASTE CHARACTERISATION SYSTEM - 16361
J. A. Mason, M. R. Looman, and R. Price, A. N. TechnologyLtd.(UK)
This paper describes the design and operation of the Combined Technology Automated Waste Characterisation System (CTA-
WCS) at JRC Ispra. <strong>The</strong> WCS was designed for the measurement of fission products and uranium and plutonium containing waste
arising from nuclear fuel and nuclear materials processing and reactor operations. <strong>The</strong> WCS covers a range of activity including
Low and Intermediate Level Waste (LLW and ILW). <strong>The</strong> system is designed to measure the waste in 200 and 400 (440) litre drums
with a maximum drum weight of 1500 kg. Gamma-ray measurements of radio-nuclide content are performed by a gamma ray measurement
station which functions as either a Segmented Gamma Scanner (SGS) or Tomographic Segmented Gamma-ray Scanner
(TSGS). Either of these two techniques may be employed to perform the functions of drum screening, non-destructive examination
(NDE) and, where appropriate, final drum assay. Coupled to the gamma ray station is a surface dose-rate measurement station,
which employs 6-shielded Geiger-Muller detectors. Active and passive neutron measurements are performed by an advanced,
graphite lined Differential Die-away (DDA) system, which comprises the neutron measurement station. <strong>The</strong> DDA performs conventional
passive neutron totals, coincidence, and multiplicity counting and active DDA total neutron counting. Data analysis is
based on the use of a range of matrix calibrations, some determined by Monte Carlo analysis. Linking the gamma ray and neutron
measurement stations is an automated roller conveyor with a 20 drum buffer capability and a weight measurement station. Drums
are identified by bar code reading technology. Once loaded, the system performs automatic assay of up to 20 drums and then returns
the drums to the buffer position on the conveyor. <strong>The</strong> first WCS of this type was supplied to the European Commission at the Joint
Research Centre (JRC) Ispra in northern Italy and it was commissioned at the end of 2007. It is now in a phase of pilot operation.
Results will be presented from the first drum measurement campaign.
SESSION 50 - QUALITY ASSURANCE AND CONTROL IN RADIOACTIVE WASTE MANAGEMENT
1) CONTROL OF MATERIALS HARMFUL TO WATER IN THE GERMAN KONRAD REPOSITORY - 16125
Karin Kugel, Stefan Steyer, Peter Berneckee, Bundesamt fuer Strahlenschutz (BfS (Germany);
Detlef Gruendler, Wilma Boetsch, Claudia Haider, ISTec GmbH (Germany)
In order to avoid a pollution of the near surface ground water during the post closure phase of the Konrad repository the acceptable
amount of material harmful to water in the radioactive waste is restricted. For this purpose the KONRAD plan approval order
includes waste requirements referring to the German water law (water law permission).
Our contribution is subdivided into three parts.
In the first part the water law permission for the KONRAD repository is introduced. This permission contains a list of materials
harmful to water with the respective limitations in mass and many instructions and proposals regarding the registering and balancing
of these materials as well as quality assurance aspects.
<strong>The</strong> second part deals with the implementation of the water law permission in the waste acceptance criteria. <strong>The</strong> waste producer
has to describe his waste in a standardized way with respect to the material composition. <strong>The</strong> operator of the repository has to
check this description and to register and balance the materials and substances harmful to water. This procedure is based on a standardized
list of materials and a list of containers.
<strong>The</strong> list of materials contains all materials and substances which may occur in the radioactive wastes. For each material in the
list a comprehensive description, the composition, hazard information, thresholds and other data are stated. <strong>The</strong> list of container
includes all containers and packages used for the final disposal of radioactive waste.
In our contribution both lists are introduced. <strong>The</strong> approach for the standardized description as well as the registering and balancing
procedures of the materials harmful to water are described.
In the third part quality assurance measures used for the proof of the compliance with the acceptance criteria (with respect to
the water law permission) are described. In particular objective of the quality assurance, possible quality assurance procedures and
acceptable margins are dealt with.
2) DOSE VALIDATION IN THE DUTCH INTERIM WASTE STORAGE FACILITY - 16263
Jeroen Welbergen, Leo P.M. Van Velzen, Nuclear Research and Consultancy Group (Switzerland)
All radioactive waste in the Netherlands is collected by COVRA (acronym for Central Organisation for Radioactive Waste)
that operates a facility for treatment of waste including interim storage buildings for HLW, LILW and TENORM (Calcinate and
U3O8).
Like many other waste management organisations, COVRA developed and adopted different waste storage strategies for different
types of waste. <strong>The</strong> basis of all strategies is Isolation, Control and Surveillance (ICS), a principle aimed at minimization of
dose to operators and the public alike. <strong>The</strong> stacking of waste in the storage buildings directly follows from this principle. To minimize
radiation exposure of employees, waste is stacked in blocks. In these block the packages with low dose rates are placed on
the outside and are shielding packages with higher dose rates and neutron sources inside. <strong>The</strong> packages with the lowest dose rate
are stacked against the outer walls to minimize radiation into the environment.
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Session 50-51 Abstracts
In 2004, a novel Non-Destructive Assay (NDA) method was used to validate the applied waste storage strategies in terms of
spatial dose rate distribution. With this method measurements were performed in one of the interim storage modules for LILW. <strong>The</strong>
dose rate at a height of 6m, mainly responsible for the sky-shine at the site boundary, was somewhat higher then expected.
Based on the experience and feedback, the NDA method was developed further, into the present INDSS-R (acronym for
INDoor Survey System Radiation) method.
3) SORPTION DATABASES FOR INCREASING CONFIDENCE IN PERFORMANCE ASSESSMENT - 16053
Anke Richter, Vinzenz Brendler, Cordula Nebelung,Forschungszentrum Dresden-Rossendorf e.V. (Germany);
Timothy E. Payne, Australian Nuclear Science and Technology Organization (Australia);
Thomas Brasser, GRS Braunschweig (Germany)
World-wide activities focus on the remediation of radioactively contaminated sites. One common aim is to deliver a more profound
chemical base for risk assessment, namely all those physico-chemical phenomena governing the contamination plume development
in time and space. Coupled transport codes able to tackle this challenge have to simplify the resulting very complex reaction
pattern. To do so in an adequate way requires extending the knowledge about retardation and mobilisation phenomena and the
underlying basic processes and interactions (e.g. physisorption, chemisorption, surface precipitation).
Interactions at the solid-liquid interface can be described by complementary approaches, the empirical Kd concept and the
mechanistic Surface Complexation Models (SCM).
Kds are used by most reactive transport and risk assessment codes due to the straightforward numerics involved. In addition,
the Kd concept is often the only feasible option for complex solid phases. However, the Kd concept is a rather simplistic approach.
Many very different basic physicochemical phenomena are subsumed in just one conditional parameter. <strong>The</strong>refore, extrapolating
Kd values may yield very large uncertainties.
4) DECOMMISSIONING AND WASTE TREATMENT HAZARD EVALUATION AND MODELING - 16409
Martin Plys, Michael Epstein, Fauske & Associates, LLC (USA)
Hazards encountered during decommissioning and waste treatment involve different issues, emphasis, and scenarios than
encountered during normal facility operations. This paper provides examples from experience in analysis and modeling of diverse
facilities, framed in terms of custom phenomena models and their incorporation into integral facility analysis modeling. Models for
entrainment of contamination and aerosol behavior are described and applied. <strong>The</strong> FATETM (Facility Flow, Aerosol, <strong>The</strong>rmal, and
Explosion) computer program is described, and example calculations are given for contamination release due to a dust explosion
in order to demonstrate the sensitivity to boundary conditions and the use of engineered safeguards.
SESSION 51 - VITRIFICATION AND BOROSILICATE GLASS ALTERNATIVES FOR IMMOBILIZATION
1) THE RESULTS OF TESTING TO EVALUATE CRYSTAL FORMATION AND
SETTLING IN THE COLD CRUCIBLE INDUCTION MELTER - 16282
James Marra, SRNL (USA); Sergey Stefanovsky, Dmitriy Suntsov,Vladimir Lebedev, SIA Radon (Russia)
<strong>The</strong> Cold Crucible Induction Melter (CCIM) technology offers the potential to increase waste loading for High Level Waste
(HLW) glasses leading to significant improvements in waste throughput rates compared to the reference Joule Heated Melter
(JHM). Prior to implementation of a CCIM in a production facility it is necessary to better understand processing constraints associated
with the CCIM. <strong>The</strong> glass liquidus temperature requirement and tolerance to crystal formation for processing in the CCIM
is an open issue. Testing was conducted to evaluate crystal formation and crystal settling during processing in the CCIM to gain
insight into the effects on processing. A high aluminum/high iron content glass composition with known crystal formation tendencies
was selected for testing. A continuous melter test was conducted for approximately 51 hours. To evaluate crystal formation,
glass samples were obtained from pours and from glass receipt canisters where the glass melt had varying residence time in the
melter. Additionally, upon conclusion of the testing, glass samples from the bottom of the melter were obtained to assess the degree
of crystal settling. Glass samples were characterized in an attempt to determine quantitative fractions of crystals in the glass matrix.
Crystal identity and relative composition were determined using a combination of x-ray diffraction (XRD) and scanning electron
microscopy coupled with energy dispersive spectroscopy (SEM/EDS). Select samples were also analyzed by digesting the glass
and determining the composition using inductively coupled atomic emission spectroscopy (ICP-AES). <strong>The</strong>re was evidence of crystal
formation (primarily spinels) in the melt and during cooling of the collected glass. <strong>The</strong>re was evidence of crystal settling in the
melt over the duration of the melter campaign.
2) COLD CRUCIBLE VITRIFICATION OF SRS SB4 WASTE AT HIGH WASTE LOADINGS - 16197
Sergey Stefanovsky, Alexander Kobelev, Vladimir Lebedev,Michael Polkanov, Oleg Knyazev, SIA Radon (Russia);
James Marra, SRNL (USA)
<strong>The</strong> test on determination of maximized waste loading was performed at the Radon bench-scale facility equipped with a 236
mm inner diameter cold crucible. Waste surrogate was vitrified using a commercially available Frit 503-R4 (in wt.%: 8 Li2O, 16
B2O3 , 76 SiO2 ). Waste loading ranged between ~45 and 70 wt.%. Viscosity of the melt with 50 wt.% waste loading remains lower
100 Poises (maximum value for glass melting) even at temperatures below 1300 oC. Electric resistivity value for this glass allows
electric melting at temperatures of 1100-1150 oC and higher. Melt viscosity increases with the increase of waste loading and glass
with 60 wt.% waste loading has appropriate viscosity for melting at temperatures over 1350 oC. This glass is much shorter than the
glass with 50 wt.% waste loading. Its electric resistivity at the same temperature is higher than that of glass with 50 wt.% waste
loading and allows to produce this glass at temperatures 1250 oC and lower, but high viscosity is a restricting factor and this glass
requires for its production temperatures ~ 1400 oC and over. <strong>The</strong> melt with 70 wt.% waste loading is too inhomogeneous and viscous
and its viscosity and electric resistivity cannot be measured precisely. As a result the glasses with 70 and 60 wt.% waste load-
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ings require melting temperature as many as 1350-1400 oC whereas the glass with 50 wt.% waste loading may be produced at 1150-
1250 oC. Wet slurry (~50 and ~70 wt.% water content) in amount of 625.1 kg was processed and glass in amount of 186.6 kg was
produced and poured into 12 canisters for 91 hrs. Average slurry feed rate, glass productivity and specific glass productivity were
6.86 kg/hr, 2.16 kg/hr, and 68.8 kg/(m2 ×hr) respectively.
3) ON FLUIDIZATION OF BOROSILICATE GLASSES IN INTENSE RADIATION FIELDS - 16055
Michael Ojovan, Guenter Möbus, Jim Tsai, Stuart Cook, University of Sheffield (UK);
Guang Yang, University of Chicago (USA)
<strong>The</strong> viscosity is rate-limiting for many processes in glassy materials such as homogenisation and crystallisation. Changes in
the viscous flow behavior in conditions of long-term irradiation are of particular interest for glassy materials used in nuclear installations
as well as for nuclear waste immobilising glasses. We analyse the viscous flow behavior of oxide amorphous materials in
conditions of electron-irradiation using the congruent bond lattice model of oxide materials accounting for the flow-mediating role
of broken bonds termed configurons. An explicit equation of viscosity was obtained which is in agreement with experimental data
for non-irradiated glasses and shows for irradiated glasses, first, a significant decrease of viscosity, and, second, a stepwise reduction
of the activation energy of flow. An equation for glass-transition temperature was derived which shows that irradiated glasses
have lower glass transition temperatures. Intensive electron irradiation of glasses causes their fluidisation due to non-thermal bond
breaking and can occur below the glass transition temperature. Due to surface tension forces fluidisation of glasses at enough high
electron flux densities can result in modification of nano-size volumes and particles such as those experimentally observed under
TEM electron beams.
4) DESIGN INNOVATIONS IN ADVANCED VITRIFICATION SYSTEM AT TARAPUR - 16254
Kalyan Banerjee, Rajendra Gupta, Sudhakaran Nair, Sridutt Misra, Bhabha Atomic Research Centre (India)
Glass has been chosen internationally by most countries as the final waste form for disposal of high level waste (HLW) because
the glass matrix is chemically inert and can accommodate a wide spectrum of radio-nuclides. <strong>The</strong> process, universally referred to,
as vitrification, is very tolerant of expected compositional variations in HLW and has been adopted as a reference process in several
countries over the past fifty years. Liquid high-level wastes are mixed with glassforming chemicals, melted and poured into
robust stainless steel canisters which are then sealed by welding. All these operations are carried out remotely in shielded hot cells
since HLW is highly radioactive. Glass offers sound product characteristics, which are extremely essential for the long-term disposal
in deep geological repositories. <strong>The</strong> last forty years have seen the glass process evolving from small batch operations, to the
presently existing high capacity continuous processes. Single step vitrification process using ceramic melters provides an appreciable
simplification of the whole vitrification process. <strong>The</strong> high energy input into the molten glass pool achieves drying, calcination
and melting in a single piece of process equipment. <strong>The</strong> process is continuous and favours considerably high feed throughputs. With
the Indian atomic energy programme maturing with substantial increase in HLW generation, the ceramic melter technology is
expected to become the preferred process in near future when work begins on the construction of several integrated facilities for
reprocessing and vitrification.
<strong>The</strong> first plant based on the ceramic melter technology named as Advanced Vitrification System (AVS) was designed, installed
and commissioned in the process cells of the Solid Storage Surveillance Facility (SSSF), Tarapur. Since the plant was hot commissioned,
the AVS has successfully produced about 175 m3 of vitrified high level waste. This paper describes the design experience
of AVS and how the lessons learnt during its operation have helped in modifications of future plants.
5) THE EFFECT OF WASTE LOADING ON THE CHARACTERISTICS
OF BOROSILICATE SRS SB4 WASTE GLASSES - 16196
Sergey Stefanovsky, Alexander Kobelev, Vladimir Lebedev, Michael Polkanov,
Dmitriy Suntsov, SIA Radon (Russia); James Marra, SRNL (USA)
<strong>The</strong> glasses containing surrogate of Sludge Batch 4 (SB4) waste with high concentrations of aluminum and ferrous oxides
within the waste loading range of ~50 to 70 wt.% produced in a 236 mm inner diameter cold crucible were examined by X-ray diffraction,
electron microscopy and infra-red spectroscopy. At relatively low waste loadings (50 to 60 w.%) the products remain predominantly
vitreous with minor crystalline spinel structure phase corresponding in chemical composition to trevorite-magnetite
solid solution. At higher waste loadings (>60 wt.%) amount of crystalline phases increased significantly and extra nepheline phase
occurred. <strong>The</strong> products with of 65 to 70 wt.% waste loading are spinel/nepheline glass-ceramics. <strong>The</strong> glass with 60 wt.% waste
loading slowly cooled in accordance with the canister centerline cooling (CCC) conditions contains minor nepheline. Occurrence
of nepheline reduces chemical durability of nuclear waste glasses.
6) DIFFUSION OF HELIUM IN BOROSILICATE GLASSES: A COMPARATIVE APPROACH BETWEEN
RADIOACTIVE AND NON-RADIOACTIVE GLASSES - 16208
Toby Fares, Sylvain Peuget, Atomic Energy Commission (CEAMarcoule) (France);
Jacques Haussy, CEA (France); Xavier Deschanels, ICSM (France)
High-level nuclear wastes consisting mostly of fission products and minor actinides are currently vitrified. A borosilicate glass
has been selected in France as the reference waste conditioning matrix. Because the glass canisters will be placed in a geological
repository, research is carried out to predict the long-term behavior of the glass under disposal conditions. <strong>The</strong> main source of radiation
damage (atomic displacements) inside the glass is caused by the ~-decay mode of the minor actinides (Am and Cm). Each ~disintegration
generates a helium atom that could induce an increase of helium concentration over time in the glass network. Investigating
the diffusion of helium in the glass is therefore important to understand the mechanisms involved in long term helium
behavior. <strong>The</strong>se mechanisms will allow us to predict whether or not helium will be released outside the glass under geological conditions;
if release does not occur, the issue of bubble formation in the glass structure must be evaluated. This paper presents some
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results on helium diffusion obtained by two different studies: on 244Cm-doped glass and on glasses implanted with helium ions.
Helium diffusion coefficients were determined by modeling the experimental results obtained. <strong>The</strong> physical characteristics which
one can withdraw from each technique regarding helium diffusion were underlined. <strong>The</strong> results were compared also with those
obtained on damage and undamaged samples from the literature to assess the specific effect of glass damage on helium diffusion.
7) UNDERSTANDING POTENTIAL RELEASE MECHANISMS OF VOLATILE RUTHENIUM
DURING THE VITRIFICATION OF HIGH LEVEL WASTE - 16288
Chris Brookes, Sellafield Ltd (UK); Yvonne Lawson, Mark Sarsfield, National Nuclear Laboratory (UK);
Carl Steele, Sellafield Ltd. (UK)
In the U.K., High Level Waste from reprocessing operations is vitrified at the Sellafield Waste Vitrification Plant (WVP). A
small number of the nuclides present in the waste have the potential to volatilize during vitrification. In order to prevent release of
any radionuclides to the environment it is important to understand the mechanisms by which volatilization may occur and to have
suitable controls in place. One element of particular concern is ruthenium, formed during the fission of nuclear fuel, which has the
potential to form gaseous species such as RuO4 during the vitrification process and whose behavior must therefore be understood
in order to underpin the safe operation of WVP.
SESSION 52 - A SYNOPSIS OF KNOWLEDGE MANAGEMENT SYSTEMS
1) USE OF THE SAFETY CASE TO FOCUS KMS APPLICATIONS - 16348
Hideaki Osawa, Kazumasa Hioki, Hiroyuki Umeki, Japan Atomic Energy Agency (Japan);
Hiroyasu Takase, Quintessa Japan, (Japan); Ian McKinley, McKinley Consulting (Switzerland)
<strong>The</strong> safety case, as defined in Japan, is an integrated set of arguments to show that a repository is sufficiently safe during both
operational and post-closure phases. It explicitly includes the findings of a safety assessment and a demonstration of confidence in
these findings. It is developed in a stepwise manner, with provisional cases used to support decisions at major project milestones.
Social acceptance is acknowledged to be critical and hence a safety case includes not only technical components, but also the arguments
required to explain fundamental issues to all key stakeholders.
In the JAEA KMS project, the safety case has been found useful as a framework that allows all supporting R&D to be seen in
the context of its applicability. Various tools have been examined to develop associated argumentation models and they have been
seen to provide an overview that is valuable to both the users and producers of knowledge. <strong>The</strong> paper will review progress to date
in this work, with illustrative examples of argumentation networks and an outline of future developments and challenges.
2) PRACTICAL APPLICATION OF THE KMS: 1) TOTAL SYSTEM PERFORMANCE ASSESSMENT - 16349
Hitoshi Makino, Kazumasa Hioki, Hiroyuki Umeki, Japan Atomic Energy Agency (Japan);
Hongzhi Yang, Hiroyasu Takase, Quintessa Japan (Japan); Ian McKinley, McKinley Consulting (Switzerland)
Comprehensive total system performance assessment (PA) is a key component of the safety case. Within this PA there are a
number of tasks that reuse specific models and datasets, together with associated knowledge base for the disposal system considered.
<strong>The</strong>se are tasks where recent developments in the JAEA KMS can lead to optimisation of procedures. This paper will outline
the reformulation of PA as a Knowledge Management (KM) task, discuss application of knowledge management technologies to
PA tasks, and illustrate how these can be handled electronically in a Performance assessment All-In-one Report System (PAIRS)utilizing
hyperlinks and embedded tools to minimise duplication of material, ease Quality Assurance (QA) and facilitate the regular
updating required in the Japanese programme.
3) PRACTICAL APPLICATION OF THE KMS: 2) SITE CHARACTERISATION - 16355
Takeshi Semba, Hideaki Osawa, Kazumasa Hioki, Japan Atomic Energy Agency (Japan);
Shoko Tachibana, Hiroyasu Takase, Quintessa Japan (Japan); Ian McKinley, McKinley Consulting (Switzerland)
<strong>The</strong> characterisation of potential repository sites is one of the most resource-intensive and politically-sensitive tasks facing the
Japanese geological disposal programme. This work will produce huge volumes of information that must be correlated, quality
assured, integrated, analysed, documented and archived in a rigorous and efficient manner (a process often referred to as geosynthesis).
While some of this work involves rather routine data handling that may be easily automated, much of it requires input of
tacit knowledge which involves the experience of expert staff. In particular, planning and managing the characterisation programme
results in challenges due to the inherent uncertainty in site understanding and the inevitable surprises that will occur.
To provide support for the Japanese implementer (NUMO), which may need to run several field programmes in parallel and
also the regulator, which is supposed to follow these and provide input for key decisions, JAEA is attempting to capture both Japanese
and international geosynthesis experience within a KMS framework (termed ISIS). Although a hybrid system that combines
smartsoftware with human experts is required, the aim is to capture expert knowledge within expert systems to the maximum extent
practicable. Initial tests, based mainly on field work carried out by JAEA at the sites of the Mizunami and Horonobe underground
research laboratories, have utilised expert systems as modules in a blackboard systemapproach to planning or implementing the
processing of field data. Examples will be presented of sub-systems where this approach has already been demonstrated and perspectives
for more extensive application to integrated geosynthesis management will be discussed.
4) CHALLENGES FOR THE JAEA KMS: FOSTERING INVENTIVE DESIGN AND PROBLEM SOLVING - 16351
Hitoshi Makino, Kazumasa Hioki, Hiroyuki Umeki, Japan Atomic Energy Agency (Japan); Shoko Tachibana, Hiroyasu
Takase, Quintessa Japan (Japan); Ian McKinley, McKinley Consulting (Switzerland)
<strong>The</strong> Knowledge Management System by Japan Atomic Energy Agency (JAEA KMS) is being developed to be flexible and
able to respond to potential changes of boundary conditions. On a shorter timescale, the KMS must encourage flexibility in the
methodology used for carrying out and presenting performance assessments. This is closely linked to development of advanced
repository concepts; considering the requirements for a safe and practical repository tailored to specific site conditions, which
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reflects evolving technology. <strong>The</strong>se coupled development tasks were, in the past, carried out by expert teams in a rather informal
manner. As the technical challenges increase and the need for transparency is accepted — a more formal method of developing
innovative design solutions is needed. A knowledge engineering approach that is used in other financial and industrial applications
has thus been tested for its usefulness for such tasks.
5) OVERVIEW OF THE JAEA KMS (KNOWLEDGE MANAGEMENT SYSTEM) SUPPORTING
IMPLEMENTATION AND REGULATION OF GEOLOGICAL DISPOSAL IN JAPAN - 16354
Hiroyuki Umeki, Kazumasa Hioki, Japan Atomic Energy Agency (Japan);
Hiroyasu Takase, Quintessa Japan (Japan); Ian McKinley, McKinley Consulting (Switzerland)
<strong>The</strong> exponential growth in the knowledge base for radioactive waste management is a cause for concern in many national programmes.
In Japan, this problem is exacerbated by a volunteering approach to siting of a deep geological repository, which requires
particular flexibility in the tailoring of site characterisation plans, repository concepts and associated performance assessments.
Recognition of this situation led, in 2005, to initiation by Japan Atomic Energy Agency (JAEA) of an ambitious project to develop
an advanced Knowledge Management System (KMS) aimed to facilitate its role as the supplier of background R&D support to
both regulators and implementers of geological disposal. This overview outlines the boundary conditions and milestones for the
Japanese radioactive waste management programmes, the roles of key organisations and the particular responsibilities of JAEA that
led to definition of the goals of the KMS.
SESSION 53 - PANEL: FUTURE DIRECTIONS IN KNOWLEDGE MANAGEMENT
ABSTRACTS NOT REQUIRED
SESSION 54 - D&D TECHNOLOGIES - PART 2 OF 2
1) ADVANCED RADIOACTIVE SOIL SCREENING AND SORTING TECHNOLOGY - 16283
Jeffrey W. Lively, Michael R. Marcial, MACTEC (USA); Mark Liddiard, Worley Parsons (UK);
Javid Kelley, MACTEC (USA); Joseph Toole, Worley Parsons (UK)
Nuclear sites undergoing decommissioning typically have large volumes of soil which are heterogeneously contaminated by
radioactivity from historic operations. <strong>The</strong>re is a severe shortage of available disposal space for this type of material in the United
Kingdom (UK) and worldwide. It is, therefore, important that volumes being disposed are minimised as far as possible to ensure
efficient use of scarcely available radioactive waste disposal facilities. <strong>The</strong>re are also significant cost savings to be realised from
segregating clean and exempt material from material classified as low-level (radioactive) waste (LLW) for disposal in other (nonradioactive)
facilities or preferably for recycling onsite as part of the site closure process.
<strong>The</strong> use of a proven dynamic measurement and soil sorting technology has the potential to speed up site closure, reduce LLW
volumes, and save the decommissioning programmes significant costs. Conveyor-based, radiological soil measurement systems
developed have been used to process bulk soils with the potential to be contaminated with radioactivity, segregating soils that
exceed the accepted regulatory limits from those that could be reused onsite or otherwise disposed in non-radioactive disposal facilities.
This paper will describe the operation and advanced capabilities of MACTEC’s state-of-the-science bulk soil survey and sorting
system developed and successfully used in the USA to minimize radioactive soil waste volumes.
2) FLUORESCENCE SPECTRAL IMAGING AS A TOOL FOR LOCATING
URANIUM DEPOSITED ON SURFACES - 16089
David L. Monts, Institute for Clean Energy Technology (ICET)(USA);
Guangjun Wang, Yi Su, Ping-Rey Jang, Charles A. Waggoner, ICET (USA)
In the environment, metallic uranium readily oxidizes to form uranium compounds that contain the uranyl (UO +2
2 ) moiety. For
more than a hundred and fifty years, it has been known that when illuminated with ultraviolet (UV) light, uranyl compounds exhibit
characteristic fluorescence in the visible region (450-650 nm). We report our efforts to develop a transportable, quantitative Fluorescence
Spectral Imaging (FSI) system as a tool for locating and quantifying uranyl compounds dispersed in soils and on other
surfaces. A project is underway to develop a set of sensors to locate expended depleted uranium (DU) rounds and to process soil
and debris to recover the material from domestic firing ranges. <strong>The</strong> FSI system can also be utilized to monitor excavation of DU
munitions and separation of uranyl compounds from soils. FSI images are acquired by illuminating a surface with a UV light and
using a narrow bandpass filter on a camera, recording an image of the resulting fluorescence. <strong>The</strong> FSI image provides both spatial
and spectral information. <strong>The</strong> FSI system is described and its performance characterized using field samples.
3) SURFACE DECONTAMINATION BY PHOTOCATALYSIS - 16068
R. J. Wilbraham, C. Boxall, Lancaster University (UK): R. J. Taylor, National Nuclear Laboratory (UK)
Currently in the nuclear industry, surface contamination in the form of radioactive metal or metal oxide deposits is most commonly
removed by chemical decontamination, electrochemical decontamination or physical attrition. Physical attrition techniques
are generally used on structural materials (concrete, plaster), with (electro)chemical methods being used to decontaminate metallic
or painted surfaces. <strong>The</strong> most common types of (electro)chemical decontamination are the use of simple mineral acids such as nitric
acid or cerium (IV) oxidation (MEDOC). Use of both of these reagents frequently results in the dissolution of a layer of the substrate
surface increasing the percentage of secondary waste which leads to burdens on downstream effluent treatment and waste
management plants. In this context, both mineral acids and MEDOC can be indiscriminate in the surfaces attacked during deployment,
e.g. attacking in transit through a pipe system to the site of contamination resulting in both diminished effect of the decontaminating
reagent upon arrival at its target site and an increased secondary waste management requirement. This provides two main
requirements for a more ideal decontamination reagent: Improved area specificity and a dissolution power equal to or greater than
the previously mentioned current decontaminants.
Photochemically promoted processes may provide such a decontamination technique.
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Session 54-55 Abstracts
Photochemical reduction of metal ion valence states to aid in heavy metal deposition has already been extensively studied [1],
with reductive manipulation also being achieved with uranium and plutonium simulants (Ce) [2]. Importantly photooxidation of a
variety of metals, including neptunium [3], has also been achieved. Here we report on the potential application of this technology
to metal dissolution.
4) THE DEVELOPMENT OF A PROTOTYPE OF A MULTI-ARM ROBOTIC SYSTEM FOR DECONTAMINATION
AND DECOMMISSIONING (D&D) APPLICATIONS WITHIN THE NUCLEAR INDUSTRY - 16017
Mohamed J. Bakari, Derek W. Seward, Taylor C. James,Lancaster University (UK)
<strong>The</strong>re are many challenges that will be faced for decades to come in the development of remote handling and robotics for the
nuclear industry in the UK. This paper discusses the development of a robotic system for D&D applications.
With the use of the modern development path of robotics, this paper shows that MARS-ND is a good example of a robotic system
specifically designed for decommissioning applications. <strong>The</strong> paper will also demonstrate the complexity of such a system by
considering a number of aspects including the need for mobility; control; sensors; effective system design; and integration using
modern tools that are available „off-the-shelf‟, or to be ordered with modified specifications to meet the design requirements for
use in D&D application. <strong>The</strong>se modern tools allow a single mechatronics engineer to design, integrate, interface, build and develop
a high-level control system when compared to the traditional way of building a similar robot.
5) A REVIEW OF VORTEX AMPLIFIER DESIGN IN THE CONTEXT OF
SELLAFIELD NUCLEAR OPERATIONS - 16063
Martin Birch, John Tyndall Institute of Nuclear Research (UK); Raymond Doing, Sellafield Limited (UK);
Johathan Francis, University of Central Lancashire (UK); Darren Parker, Land Securities Trillium (UK);
Guobin Zhang, School of Electrical and Electronic Engineering (UK)
Vortex amplifiers have for over 30 years been used to ensure containment of glove-box ventilation in the event of a barrier
breach, the most likely such breach being damage to the glove itself. Containment is achieved using fluidic principles to control
the glove-box depression and ventilation rate under both normal and emergency conditions; in the event of such a breach vortex
amplifiers can switch quickly between these two states without recourse to electrical, pneumatic or manual intervention.
This paper begins by summarising the developments in vortex amplifier design used at the Sellafield site by successive companies
engaged in fuel technology, reprocessing and decommissioning (British Nuclear Fuels PLC (BNFL), BNFL Engineering
Limited, British Nuclear Group and Sellafield Limited). <strong>The</strong> main reasons for design changes have been practical issues of set-up,
cleaning, filter and waste minimisation, and space limitations. <strong>The</strong> development culminates in the use of a smaller version of the
vortex amplifier (VXA) which is a nearly exact geometrical scaling of its predecessor and which has been standard design for over
a decade. Initial use of this device, the mini-VXA, led to a substantial increase in the amount of inert gas needed to maintain the
required oxygen-depletion conditions within the glove-box, implying some escape.
6) DEVELOPMENTS IN THE LONG TERM PRESERVATION OF DIGITAL INFORMATION
FOR NUCLEAR DECOMMISSIONING - 16412
Jon Tilbury, Christina Tealdi, Tessella, (UK)
<strong>The</strong> biggest threat to providing long term access to this managed information is the rate of technology evolution. <strong>The</strong> files and
datasets generated today may be unreadable by the software and systems in use in one or two decades. Also data is increasingly
complex with intricate interdependences between data objects, for example web sites and CAD drawings. Also, digital objects
increasingly have behaviours that mean printing to paper or non-interactive formats such as PDF, may result in vital information
being lost. <strong>The</strong> need for sophisticated active preservation of these records is thus essential.
<strong>The</strong> nuclear industry is not alone in facing these challenges and much pioneering work has been performed in academia and
by national archives and libraries. In order to perform long-term digital preservation, it is necessary to (i) understand the technology
of the material being stored, (ii) be able to decide whether this technology is obsolete (and if so, what to do about it) and (iii)
perform verifiable actions to remove the causes of this obsolescence (e.g. via format migration) or (iv) provide new approaches to
delivering environments in which the original software can run (e.g. via hardware emulation).
This paper will cover developments in the digital preservation and archiving field based on this pioneering work. It will draw
on the lessons of EC funded research projects such as Planets and KEEP. It will also present the lessons from national archive initiatives
in the UK, Netherlands Switzerland and beyond, and show how these are applicable to the nuclear industry.
SESSION 55 - REGULATORY COMPLIANCE, RADIOLOGICAL SURVEYS, AND FACILITY RELEASE
1) RADIOLOGICAL, TECHNICAL AND FINANCIAL PLANNING FOR DECOMMISSIONING
OF SMALL NUCLEAR FACILITIES IN SWEDEN - 16177
Rolf Sjöblom, Tekedo AB (Sweden); Staffan Lindskog, Swedish Radiation Safety Authority (Sweden)
On November 1st 2008, a new ordinance came into force in Sweden. It extends the implementation of nuclear liability to all
nuclear facilities and companies, regardless of size. <strong>The</strong> Government has authorized the Swedish Radiation Safety Authority (SSM)
to issue further regulation as warranted and appropriate, and commissioned the same Authority to oversee the implementation.
Consequently, SSM is presently conducting research in order to establish a basis for the implementation of the ordinance to
smaller facilities and enterprises. <strong>The</strong> goal is to enable finance to be assured in an efficient manner so that any burden on the companies
can become as small as possible.
Thus, functional requirements are identified, and used as a basis for various investigations. <strong>The</strong> aspects include technical and
cost calculation prerequisites, as well as various domains of law: the environmental code, radiation and nuclear safety, financial
reporting, and criminal law.
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Abstracts Session 55
It is found that the basis for the differentiation among the facility operators and owners should be the cost and the associated
uncertainty. Thus, cost calculation will have to be carried out by all. It should be based on available standards and guidance documents.
It is found that this is a requirement that already exists elsewhere in the legislation, and thus no additional burden is imposed
on the companies.
2) MARSAME: MULTI-AGENCY RADIATION SURVEY AND ASSESSMENT
OF MATERIALS AND EQUIPMENT - 16181
Kathryn Snead, Nidal Azzam, U.S. Environmental Protection Agency (USA);
Colleen F. Petullo, U.S. Public Health Service (USA); Ramachandra Bhat, Craig Bias, U.S. Air Force (USA);
David P. Alberth, Gerald Falo, U.S. Army, Aberdeen Proving Ground (USA);
Steven Doremus, U.S. Navy, Yorktown (USA);
W. Alexander Williams, Amanda Anderson, U.S. Department of Energy (USA);
Robert A. Meck, George E. Powers, U.S. Nuclear Regulatory Commission (USA)
<strong>The</strong> MARSAME manual is a technical resource that describes processes and methods for the measurement of radionuclides in or
on materials and equipment. <strong>The</strong>se methods and processes are used to make the decision that a radionuclide is present and, if so, how
to quantify the amount and its uncertainty. <strong>The</strong>y are also used to make the decision that no radionuclide more than background is present.
<strong>The</strong> MARSAME manual is technically defensible, and endorsed by the U.S. Department of Defense, the U.S. Department of Energy,
the U.S. Environmental Protection Agency, and the U.S. Nuclear Regulatory Commission. <strong>The</strong> MARSAME manual was published
in January 2009, and is available for download from the following website: http://www.epa.gov/rpdweb00/marssim/marsame.html.
<strong>The</strong> MARSAME manual is a supplement to the MARSSIM manual, and closely follows the concepts and processes developed
therein. <strong>The</strong> MARSSIM manual describes processes and methods for the measurement of radionuclides on the surfaces of buildings
and soils.
3) DETERMINATION OF THE RADIONUCLIDE INVENTORY OF SAMPLES
FROM A SPALLATION NEUTRON SOURCE - 16225
Dorothea Schumann, Paul Scherrer Institute (Switzerland)
<strong>The</strong> Paul Scherrer Institute (PSI) in Villigen (Switzerland) operates the most powerful spallation neutron source (SINQ) in
Europe and also world-wide. A 590-MeV-ringcyclotron accelerates protons with a beam current of 2 mA which hit a solid lead target.
An upgrate of the accelerator complex to 3.5 mA is foreseen in the near future.
In such huge accelerator facilities, the safe operation as well as the handling of the nuclear waste in the case of dismantling,
decommissioning and/or disposal of activated components requires reliable data on the radionuclide inventory.
<strong>The</strong> spallation neutron source SINQ represents in this context a special issue, because the lead target serves in principle as a
big “beam dump”, which means that the beam particles are completely stopped and the entire energy deposit has to be expected in
the target body and the surrounding environment. Accurate determination of the activation in this area is therefore of essential
importance.
We report here on the radiochemical analysis of three componential parts of the SINQ target setup and environment. <strong>The</strong> materials
are zircaloy, stainless steel and AlMg3 . 20 radionuclides were determined by gamma-spectrometry, Liquid Scintillation Counting
(LSC) technique as well as Accelerator Mass Spectrometry (AMS). Some of these isotopes can only be measured after a complex
chemical separation procedure. <strong>The</strong> results are compared with the declaration limits and the activity limits for decommissioning.
It is shown that all determined radionuclides have to be declared, but no problems have to be expected for decommissioning
and disposal.
4) MEASUREMENT OF RADIOACTIVE AEROSOL BEHAVIOR DURING DISMANTLING
AND REFLECTION TO THE EXPOSURE DOSE EVALUATION - 16107
Yukihiro Iguchi, Masami Kato, Japan Nuclear Energy Safety Organization (Japan)
Radioactive aerosol disperses slightly via contamination prevention systems such as control enclosures and filters when the
nuclear installation is dismantled, and it might impact the environment. <strong>The</strong>refore, when decommissioning is planned, it is necessary
to assess the safety such as exposure dose evaluation to the public. For the radioactive aerosol, it is possible that the dispersion
ratio is different according to the contamination condition, the dismantlement method of the material, nuclides (elements), etc.
<strong>The</strong> radiation exposure evaluation for the decommissioning plan has been executed by operators in Japan based on a number
of experiments (mostly cold tests) and overseas results.
<strong>The</strong> decommissioning is now being carried out at the Tokai Power Station (GCR) and Fugen Decommissioning Engineering
Center in Japan. In this study, the results data is acquired at the decommissioning sites, and the methodology and data for the exposure
dose evaluation are verified and confirmed. <strong>The</strong>se examination results will lead to the upgrading and improvement of the exposure
evaluation methodology.
5) IAEA DECOMMISSIONING SAFETY ACTIVITIES - 16397
Vladan Ljubenov, Ernst Warnecke, Mark Hannan, <strong>International</strong> Atomic Energy Agency (Austria)
This paper presents a summary of the recent, ongoing and planned safety related IAEA activities on planning, implementation
and termination of decommissioning. Work related to the Joint Convention on the Safety of Spent Fuel Management and on the
Safety of Radioactive Waste Managementand to the development of the international safety standards for decommissioning of facilities
using radioactive materials is described. <strong>The</strong> IAEA activities on the technical assistance to the Member States in the development
and review of decommissioning plans through national and international Technical Cooperation Programme projects and
through other projects (FaSa project, R2D2P Project, decommissioning of the Iraq former nuclear complex) are presented. Recently
established IAEA peer review services on decommissioning are addressed, as well as the international decommissioning forum.
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Session 55-56 Abstracts
6) PLASMA ARC CUTTING EXPERIMENTS USING RADIOACTIVE MATERIALS FOR EVALUATION OF
AIRBORNE DISPERSION RATIO - 16106
Taro Shimada, Japan Atomic Energy Agency (Japan); Atsushi Takamura, Science System Laboratory (Japan); Atsushi
Kamiya, Nihon Advanced Technology (Japan); Takenori Sukegawa, Tadao Tanaka, Japan Atomic Energy Agency (Japan)
Experiments for airborne dispersion ratio of radionuclides during plasma arc cutting were carried out in a contamination control
enclosure, using stored radioactive metal wastes arising from the decommissioning activities of Japan Power Demonstration
Reactor, which was a boiling water type reactor. Neutron induced-activated piping and surface contaminated piping were segmented
into pieces using air plasma arc cutting, using a current power was 100A. In addition, similar experiments for contaminated piping
of the Advanced <strong>The</strong>rmal Reactor, Fugen were carried out.
As a result, dispersion ratios for activated piping were 0.2 to 0.7% of Co-60 and 0.4% of Ni-63 under the condition with a covered
cap on the head. And those for surface contaminated piping were from 18 to 23%. In addition, those for vertically segmented
piping which simulated flat plate were from 34 to 43%. <strong>The</strong>re was no difference of dispersion ratios between stainless steel and
carbon steel base materials. All values obtained were smaller than the Handbook recommended value of 70% for contaminated
materials.
7) THE DEVELOPMENT AND EFFICACY OF THE CONTINUED OPERATIONS SAFETY REPORT - 16067
Jonathan Francis, University of Central Lancashire (UK); Gavin Smith, Sellafield Limited (UK);
Ian D Nickson, John Tyndall Institute for Nuclear Research (UK)
<strong>The</strong> requirement to build a safety case is fundamental to the public governance of nuclear sites. Through the Nuclear Safety
Directorate, the public permits operators of nuclear licensed sites to design, build, operate, decommission, dismantle (and manage
the waste arising from) a facility and ultimately remediate the site. <strong>The</strong> Health & Safety Executive has published a plethora of material
to explain the principles of the permissioning philosophy; the non-prescriptive approach by which operators are led to consider
and manage risks and develop safe operating procedures.
Since before the turn of the Millenium, there has been ongoing and relatively rapid change in the ownership and organisational
structure of those charged with operating and/or decommissioning at the Sellafield site. <strong>The</strong> potential for this change to affect
operations, record and documentary control systems and consequently, the possible threat to the maintenance of design intent led
to the development of a new process: the Continued Operations Safety Report (COSR).
8) PLANNING FOR DECOMMISSIONING OF AN IRRADIATION FACILITY USED
FOR RESEARCH PURPOSES IN CUBA - 16120
Juan Carlos Benitez-Navarro, Mercedes Salgado-Mojena,CPHR (Cuba);
Evelio Soto Alvarez, Daniel Fraga Acosta, CENSA (Cuba); Jose Quevedo, Yolanda Perez, CNSN (Cuba)
<strong>The</strong> National Center for Animal Health (CENSA) used an irradiator (model Gammacell 500) for sterilizing medical and pharmaceutical
devices and supplies. <strong>The</strong> facility was commissioned in 1989 and was in operation until 2008. It has to be shut down as
the safety mechanisms might become not effective.
According to Cuban regulations, the Institution has to apply for a Decommissioning Licence. For that, the following documents
should be prepared and presented to the Regulatory Authority: Plan for shutting down, Decommissioning plan and Safety Manual.
<strong>The</strong> institution (CENSA) requested the decommissioning services to the Center for Radiation Protection and Hygiene (CPHR).
<strong>The</strong> irradiator facility Gammacell 500 contains twelve Co-60 radioactive sources, model C-198. <strong>The</strong> total activity was 1069
TBq (28900 Ci) in December 1994, after the sources were replaced by the manufacturer. <strong>The</strong> total activity at present is less than
200 TBq. <strong>The</strong> irradiator has two compartments: a sample chamber or cylinder, where sample trays rotate around the sources when
they are loaded into this chamber (while in the irradiate position), providing dose uniformity; and the source storage container, a
lead cylindrical container located behind the sample chamber.
SESSION 56 - POSTERS: PROJECTS IN PROGRESS
1) REAL SYSTEM ANALYSES OF PA RELEVANT PROCESSES IN SEDIMENTS:
THE RUPRECHTOV NATURAL ANALOGUE SITE - 16342
Vaclava Havlova, Nuclear Research Institute Rez plc.(Czech Republic); Ulrich Noseck, Gesellschaft für Anlagen- und
Reaktorsicherheit (GRS) mbH (Germany); Melissa Denecke, Wolfgang Hauser, FZK INE (Germany), Juhani Suksi,
Helsinki University (Findland); Kazimierz Rozanski, AGH (Poland)
Component RTDC 5 of the EC Integrated Project FUNMIG (2004–2008) was aimed to study real system processes, relevant
to performance assessment (PA), in sediment formations that can form overlying layers of geological repository host rocks. <strong>The</strong>
study comprises both laboratory and in-situ work, focused on the Ruprechtov natural analogue site. <strong>The</strong> scope of scientific activities,
addressed within the frame of FUNMIG RTDC 5 is presented here. Moreover, integration of results from other components as
FUNMIG RTDC 2 into the real system description and vice versa is demonstrated.
<strong>The</strong> project scientific activities proceeded from investigation of specific issues (e.g. natural organic matter study) to a more
integral investigation and characterisation of the complex natural U system, in particular the characterisation of the immobile U
phases combining sophisticated analytical methods, and finally to generalizing real system analyses, e.g. the evaluation of hydrological,
geochemical and environmental isotope data in order to characterize the hydrogeological flow regime and the carbon chemistry
in the system.
128

Abstracts Session 56-57
2) A TRULY INDUSTRIAL SOLUTION FOR THE ELIMINATION OF RADIOACTIVE
CONTAMINATED OILS OR SOLVENTS - 16232
Albert Jacobs, William Everett, Dewdrops (UK)
Dewdrops has developed and tested in a fully operational pilot plant a biological process capable of eliminating a wide range
of mixtures of radioactive oils and solvents. Together with a volume reduction factor of at least 20 times, the process combines reliability
and versatility with a minimal environmental footprint. <strong>The</strong> nominal capacity of the standard mobile plant is 100 litres per
day with the actual production depending on the exact nature of the liquid to be treated. This paper will outline the main features
of the technology then concentrate on the validation tests designed to demonstrate the feasibility for any particular site, waste stream
or arising.
<strong>The</strong> DEWDROPS patented process exploits bacterial metabolisms which use oils or solvents as their vital carbon source. Carefully
selected microorganisms oxidize organic compounds to produce carbon dioxide, water and biomass. <strong>The</strong> biomass is partially
recycled in the system and the excess is eliminated at the end of the process while the water and carbon dioxide can be released to
the environment. <strong>The</strong> ultimate waste is a dry inert inorganic powder.
<strong>The</strong> originality of our process lies in the use of several specialized bacterial populations each with a different task. Crossflow
filters separate each stage maintaining bacterial population specificity and ensuring a micro-organism free outflow with a COD
(chemical oxygen demand) < 150 mg/l in complete conformance with the usual European waste water standards. Separate tests
have shown that our micro-organisms can handle radioactivity levels of at least 30 MBq/litre in the incoming oils / solvent mixtures
but the theoretical limit is much higher.
SESSION 57 - D&D OF NON-REACTOR NUCLEAR FACILITIES
1) PROGRESS AND EXPERIENCES FROM THE DECOMMISSIONING
OF THE EUROCHEMIC REPROCESSING PLANT - 16022
Robert Walthery, Wim Van Laer, Patrick Lewandowski, Nancy Reusen, Bart Ooms, Belgoprocess (Belgium)
Belgoprocess started the industrial decommissioning of the main process building of the former EUROCHEMIC reprocessing
plant in 1990, after completion of a pilot project in which two buildings were emptied and decontaminated to background levels.
<strong>The</strong> remaining structures were demolished and the concrete debris was disposed of as industrial waste and green field conditions
restored.
<strong>The</strong> Eurochemic reprocessing plant operated from 1966 to 1974 to process fuel from power reactors and research reactors. <strong>The</strong>
main building is a large concrete structure, comprising a surface area of 55,000 m², concrete volume 12,500 m³, and 1,500 Mg of
metal components. <strong>The</strong> building is divided into multiple cells. About 106 individual cell structures have to be dismantled, involving
the removal and decontamination of equipment from each cell, the decontamination of the cell walls, ceilings and floors, the
dismantling of the ventilation system.
Most of the work involves hands-on operations under protective clothing tailored to each specific task. Tool automation and
automatic positioning systems are successfully applied.
In view of the final demolition of the main process building, the main process building has been
2) DECOMMISSIONING OF BUILDINGS 105X AND 122X AT BELGOPROCESS - 16052
Bart Ooms, Robert Walthery, Bert Lievens, Wim Van Laer, Belgoprocess (Belgium)
<strong>The</strong> Eurochemic reprocessing plant was built between 1960 and 1966 and operated from 1966 until the end of 1974. During
these eight years of active operation, Eurochemic reprocessed 181.5 t of natural and slightly enriched uranium fuels (less than 4.5%
initial 235U enrichment) from various experimental and power reactors, and 30.6 t high enriched uranium fuels from testing reactors,
generating approximately 50 m³ of high-level liquid waste from power reactor fuels (LEWC, low enriched waste concentrate)
and 850 m³ from research reactor fuels (HEWC, high enriched waste concentrate). As a result of reprocessing and cleaning operations
(1975-1981), generated intermediate and high level wastes were put into temporary storage, pending the availability of appropriate
treatment, conditioning and storage facilities.
Immediately after LEWC and HEWC vitrification, the corresponding storage vessels were rinsed and decontaminated. <strong>The</strong>
rinsing and decontamination program started in April 1986 and was interrupted between September 1987 and July 1989 in view of
possibly reusing the vessels for storage of similar HLLW solutions. Because the storage building itself was not aircraft crash resistant,
it was decided not to use the storage vessels anymore and to proceed the decontamination with more aggressive chemicals. Due
to this time gap however, and especially because vitrification came to an end in September 1991, a considerable volume of decontamination
liquids was produced after this time and stored, pending the availability of the bituminization installation.
3) CLEANSING AND DISMANTLING OF CEA-SACLAY NUCLEAR LICENSED FACILITIES - 16047
Michel Jeanjacques, Rebecca Glévarec, Isabelle Tirel, Commissariat à l’Energie Atomique (France)
This summary presents the cleansing and dismantling operations currently realized on the CEA center of Saclay (CEA-Saclay).
It was initiated at the beginning of the 2000 years a cleansing and dismantling program of the old Nuclear Licensed Facilities
(NLF). Currently this program relates to the Hot Laboratories (Laboratoires de Haute Activité : LHA) and the old workshops of the
Liquid Waste Treatment Plant (Station des Effluents Liquides : STEL).
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Session 57-58 Abstracts
4) DECOMMISSIONING OF HIGH HAZARD LEGACY FACILITIES: COMPARISON
OF APPROACHES IN THE NUCLEAR AND CHEMICAL SECTORS – 16084
Trevor Jones, Nuvia Limited (UK); Des Kelly, E4 Industry (UK)
5) CHALLENGES DURING THE DECOMMISSIONING OF THE WAK SITE - DISMANTLING
OF HIGHLY CONTAMINATED HLLW-STORAGE TANKS - 16054
Joachim Dux, Oliver Fath, Belgium)WAK Rückbau- und Entsorgungs-GmbH (Germany)
he German pilot reprocessing plant WAK was shut down in 1990 after reprocessing about 200 Mg of nuclear fuels and is decided
to be dismantled completely to the green field until year 2023. During the years 1994 until 2008 approximately 2.000 Mg of
partly highly contaminated process equipment and 1.500 Mg of concrete structures corresponding to 99% of the radioactive inventory
of 5E14 Bq of the WAK reprocessing building have already been dismantled.
A major prerequisite for the complete dismantling of the WAK is the management of the 60 m³ high-level liquid waste (HLLW)
with a total β/γ -activity of 8.0E17 Bq resulting from reprocessing. For this purpose the Karlsruhe Vitrification Plant (VEK) was
constructed in the years between 2000 and 2005 and inactively tested in 2007. <strong>The</strong> subsequent nuclear test operation and routine
hot operation of the VEK plant are planned to start mid-2009.
In parallel to vitrification operation, dismantling of the four HLLW tanks in the storage buildings will be prepared for remote
dismantling.
6) URANIUM WORKSHOPS DECOMMISSIONING - 16219
Pierre Lisbonne, CEA (France)
CEA started the Enriched Uranium Treatment Workshops in 1965. <strong>The</strong>y were aimed to design and test uranium treatment
processes, and later devoted to fuel production. In the 90’, CEA decided to refocus on R and D and to transfer its production activity
to industry, hence the Enriched Uranium Workshops were shut down in July 1995.
<strong>The</strong> Post Operation Clean Out is described, and the 4 phases of dismantling equipment, infrastructures, building clean-up and
final controls are explained, as well as remediation of the outside area. Delicensing of the BNF 52 is expected in 2013.
7) FEASIBILITY STUDY INTO THE APPLICATION OF AGGRESSIVE DECONTAMINATION
TECHNIQUES IN SUPPORT OF REPROCESSING PLANT DECOMMISSIONING – 16079
Heather Moore, Sellafield Limited (UK); Stephen Hepworth, Sellafield Ltd (UK)
8) DECOMMISSIONING OF AECL WHITESHELL LABORATORIES - 16311
Grant Koroll, Randall Swartz, Jeffrey Harding, AECL (Canada); Michael Rhodes, McAlpine Enterprises (Canada);
Randall Ridgway, Dennis Bilinsky, AECL, Pinawa (Canada)
Whiteshell Laboratories (WL) is a Nuclear Research and Test Establishment near Winnipeg, Canada, operated by AECL since
the early 1960s and now under decommissioning. WL occupies approximately 4400 hectares of land and employed more than 1000
staff up to the late-1990s, when the closure decision was made. Nuclear operations carried out at WL included a research reactor,
hot cell facilities, high level nuclear fuel waste management research, reactor safety research, nuclear materials research, accelerator
technology, biophysics, and industrial radiation applications.
In preparation for decommissioning, a comprehensive environmental assessment was successfully completed and the Canadian
Nuclear Safety Commission issued a six-year decommissioning licence for WL starting in 2003 - the first decommissioning
license issued for a Nuclear Research and Test Establishment in Canada. This paper describes the progress in this first six year
licence period.
SESSION 58 - D&D MANAGEMENT APPROACHES AND PLANNING TOOLS
1) NEC3 - MANAGING CHANGE – 16380
Nick Sunderland, Hill <strong>International</strong>(UK)
<strong>The</strong> Office of Government Commerce (OGC) has endorsed the use of NEC for all public sector contracts. <strong>The</strong> reason being is
that it stimulates effective project management and enables the parties to manage risk and change more efficiently, which in turn
serves to mitigate the cost and time effects of any risk event should it arise under the contract. In essence it facilitates a more collaborative
working culture between the parties.
<strong>The</strong> NEC3 contract is gaining in popularity and has been adopted for use in the decommissioning of nuclear power stations
and the London Olympics, it also recently received support in the Tenth Special Report on Construction Matters by the House of
Commons. It has strict time limits for the notification of compensation events as set out in the core clause 61.3 whereby the Contractor’s
contract administration team needs to notify the project manager within an eight week period of becoming aware of the
event. <strong>The</strong> contract also provides for an early warning procedure whereby the Contractor and the project manager will cooperate
and proactively discuss how issues can be overcome in a collaborative manner.
This NEC3 contract requires both the Contractor and the Employer to act positively and is welcomed as a possible solution to
the entrenched disputes which have regularly occurred on major energy projects and if properly administered will hopefully result
in an earlier and less fraught final account settlement process for both parties.
130

Abstracts Session 58
2) A SUCCESSFUL TRANSITION FROM OPERATING TO DISMANTLING A UO2- PUO2 FUEL FABRICATION FACILITY – 16058
Thierry FLAMENT, Jean-Louis Lemarchand, Marc Dalmier,
Dominique Pecquais, AREVA NC (France)
After fabricating plutonium fuels for 40 years (Fast bredder reactor, Mox), commercial operations at the AREVA NC
Cadarache plant ended in 2003 and post operation clean out of its production building and laboratory started. AREVA’s objective
is to achieve IAEA level 2 clean-up of the process facilities and to transfer them to their owner, the French Atomic Energy Commission.
<strong>The</strong> completion of this operation will demonstrate the possibility to dismantle plutonium fuel fabrication facility and the
possibility to reuse the facilities.
<strong>The</strong> facilities to be dismantled by AREVA NC in Cadarache include: -422 glove boxes containing various types of equipment
(process equipment for nuclear fuel fabrication, analytical equipment to characterize fabricated fuel, process equipment to recover
valuable materials (Uranium and plutonium) and calcine liquid effluent) -38 storage tanks
<strong>The</strong> transition from commercial operation to dismantling activities was organized around the following three main steps:
3) TAILORING ENGINEERING ACTIVITIES TO D&D PROJECTS – 16056
Charles Negin, Project Enhancement Corp.(USA);
Andrew Szilagyi, Yvette Collazo, U.S. Department of Energy (USA); Charles Urland, Project Enhancement Corp. (USA);
John Gladden, Joe Santos, Savannah River National Laboratory (USA)
Engineering is an important element of Deactivation and Decommissioning (D&D) project technical planning, scheduling, estimating,
and execution. Understanding the scope of engineering and related design, deciding when in a project’s schedule these
activities should be conducted, and specifying the products to be generated from each engineering task are important management
functions. <strong>The</strong>se subjects are addressed in a guidance report developed by the U.S. Department of Energy (DOE) described in this
paper.
4) DATA TRACKING SYSTEM FOR STANDARDISED DECOMMISSIONING COSTING – 16191
Vladimir Daniska, Ivan Rehak, Peter Bezak, Frantisek Ondra, Marek Vasko, Decom, a.s. (Slovakia);
Vladimir Necas, Slovak University of Technology (Slovakia)
Implementation of the standardised cost structure (as presented in document “A Proposed Standardised List of Items for Costing
Purposes”, issued in 1999) into decommissioning projects is one of the main requirements of leading international organisations
involved in decommissioning - IAEA, OECD/NEA and European Commission. <strong>The</strong> computer code OMEGA implements this
structure as the calculation core, and the calculated cost and other decommissioning parameters (manpower, exposure, personnel,
waste items, etc.) are formatted in this structure. One of the most important outputs of the code generated by the code itself is the
Gantt chart (in Microsoft Project of Primavera software) of the decommissioning project which is the base for planning of decommissioning
activities. <strong>The</strong> standardised calculation structure of the code is universal structure applicable for any decommissioning
project while the Gantt chart is the structure specific for individual projects. <strong>The</strong> bi-directional interface between the standardised
calculation structure and the project specific Gantt chart, enables linking data between these two structures by one-to-one linking
or by grouping the selected items of the standardised structure into items of the Gantt chart. In order to improve the quality of calculated
data, a feedback system was proposed for collecting the selected data from real decommissioning and for processing the
collected data in order to improve quality of input data used for calculation, like manpower unit factors, material and media consumption,
exposure and others. <strong>The</strong> data tracking feedback system reflects the structure of the project tasks of the Gantt chart at the
lowest level, e.g. dismantling of equipment within the room. <strong>The</strong> structure of the data collected by personnel during performing the
decommissioning activities corresponds to calculation items of the standardised calculation structure which are involved in the
tasks of the Gantt chart. <strong>The</strong> paper presents the principles of the data tracking system in relation to both structures involved - the
standardised calculation structure and the Gantt chart of the decommissioning project, methods of the processing of collected data
and examples of application of the system.
5) PET CYCLOTRON DESIGN FOR DECOMMISSIONING AND WASTE INVENTORY REDUCTION – 16098
Robert Major, AMEC (UK)
In this paper we will examine the decommissioning and radioactive waste implications of a hypothetical cyclotron facility.
from conception through design into operation and finally decommissioning. Supported by the computer codes MCNPX, MCNP
and FISPACT we illustrate the induced activity in the cyclotron pit walls. Using the computer codes it is possible to highlight the
problems associated with neutron activation of the cyclotron pit walls and the need for specialist shielding materials, such as
boronated polyethylene.
Using MCNP it is possible to design a vault for cost effective decommissioning through the use of sacrificial layers. This code
allows the likely degree of activation and penetration of activation products to be quantified and hence gives an idea of waste disposal
costs.
In summary, a dedicated PET facility will challenge most RPAs. A wide range of skills are needed which encompass practical
operational procedures, through specialist shielding design using Monte Carlo codes to the ability to appear confident to Regulators
who may be finding the experience the same steep learning curve
131

Session 59 Abstracts
6) A SYSTEMATIC PLANNING TOOL FOR ENVIRONMENTAL CHARACTERISATION – 16010
Steven Wilcox, Richard I Wilkins, Martin R Lyons, AMEC (UK)
Many organisations are currently dealing with long standing legacy issues in clean up, decommissioning and demolition projects.
Industry is required to ensure that all bulk articles, substances and waste arisings are adequately characterised and assigned to
the correct disposal routes in compliance with UK legislation and best practice. It is essential that data used to support waste sentencing
is of the correct type, quality and quantity, and that it is appropriately assessed in order to support defensible, confident
decisions that account for inherent uncertainties. AMEC has adopted the Data Quality Objectives (DQO) based methodology and
the software package Visual Sample Plan (VSP) to provide a better, faster, and more cost effective approach to meeting regulatory
and client requirements, whilst minimising the time spent gathering data and assessing the information.
<strong>The</strong> DQO methodology is based on a scientific approach that requires clear objectives to be established from the outset of a
project and that there is a demonstration of acceptability of the results. Through systematic planning, the team develops acceptance
or performance criteria for the quality of the data collected and for the confidence in the final decision.
<strong>The</strong> systematic planning process promotes communication between all departments and individuals involved in the decisionmaking
process thus the planning phase gives an open and unambiguous method to support the decisions and enables the decisionmakers
(technical authorities on the materials of concern) to document all assumptions.
SESSION 59 - SAFETY CONSIDERATIONS ASSOCIATED WITH L/ILW MANAGEMENT
1) DEVELOPMENT OF JOINT REGULATORY GUIDANCE ON THE MANAGEMENT OF HIGHER ACTIVITY
RADIOACTIVE WASTES ON NUCLEAR LICENSED SITES - 16095
Michael Bacon, Health and Safety Executive (UK); Doug Ilett,Environment Agency (UK); Andrew Whittall,
ScottishEnvironment Protection Agency (UK)
In 2006 the UK Governments response1 to recommendations by its Committee on Radioactive Waste Management (CoRWM)
established, in England and Wales, that geological disposal, supported by safe and secure interim storage, is the preferred route for
the long-term management of higher-activity radioactive waste (i.e. that which is not suitable for near-surface disposal). It also gave
the responsibility for delivering the programme for a deep geological repository to the Nuclear decommissioning Authority (NDA).
<strong>The</strong> Scottish Government has a policy of long term, near site, near surface safe and secure interim storage.
To support the open and transparent approach promised by Government, the Health and Safety Executive (HSE), the Environment
Agency and the Scottish Environment Protection Agency (SEPA) are developing joint guidance on the management of higher-activity
radioactive waste to explain regulatory objectives in securing safe and secure interim storage and the associated management
of radioactive wastes. <strong>The</strong> guidance comes in two parts:
• Guidance on the regulatory process
• Technical guidance modules
2) MONTE CARLO SIMULATION OF A COMPARTMENT MODEL OF RADIONUCLIDE MIGRATION
AT A RADIOACTIVE WASTE REPOSITORY - 16168
Enrico Zio, Francesco Cadini, Diana Avram, Tommaso Girotti, Politecnico (Italy);
Alfredo Luce, ENEA CR Saluggia (Italy); Alberto Taglioni, ENEA (Italy)
Prediction of radionuclides release is a central issue in the performance assessment of nuclear waste repositories. To this aim
a model of radionuclides migration through the repository barriers must be set up, accounting for the uncertainties affecting the
process. In this context, the present paper presents the application of Monte Carlo simulation to a Markovian modeling framework
proposed in the literature; two cases are presented to highlight the value added by the flexibility of the Monte Carlo simulation
approach migration, compartment model, Monte Carlo simulation.
3) PRELIMINARY WASTE ACCEPTANCE CRITERA FOR LILW REPOSITORY IN SLOVENIA - 16115
Nadja Zeleznik, ARAO (Slovenia); Dejan Skanata, Enconet <strong>International</strong> (Croatia)
<strong>The</strong> national radwaste management agency in Slovenia (ARAO) is under course of site confirmation and designing short-lived
radwaste disposal facility. <strong>The</strong>refore, development of the waste acceptance criteria for disposal started recently. <strong>The</strong> project scope
includes review and analysis a number of references focusing in particular on those waste properties and related parameters that
may affect safety of the repository.
<strong>The</strong> waste acceptance criteria for disposal cannot be clearly defined if the site selection process and repository design are in an
early stage. In such case a request is made that waste acceptance criteria should be anticipated. Such request is logical since the
total waste management cost should be optimized. Namely, predisposal waste management capacity should be established so as to
meet all the requested acceptance criteria (treatment, storage, transport and disposal). Any omissions during the predisposal stage
shall have to be made up by additional treatment, which will certainly increase the costs.
Development of waste acceptance criteria for disposal in Slovenia has been carried out under the following main conditions:
(1) Site selection process is under way (a shortlisted site is Vrbina, Krško); (2) Basic design of repository is proposed (underground
silos); (3) Total volume of short-lived waste in Slovenia expected by 2037 is assessed to be 17,200 m3 (assessment includes operational
and decommissioning waste from Krško NPP, decommissioning waste from TRIGA, and radwaste from medicine, research
and industry); (5) Characterization of the operational waste that is storing at Krško NPP site and acceptance criteria for this storage
has been performed; and (6) Characterization of the radioactive waste from other sources that is storing at Brinje site, as well
as corresponding acceptance criteria has been established.
132

Abstracts Session 59-60
4) SAFETY EVALUATION FOR REGULATORY MANAGEMENT OF AUSTRALIAN
WASTE OPERATIONS FACILITIES - 16236
Samir Sarkar, Australian Radiation Protection and Nuclear Safety Agency (Australia)
This paper describes the approach of Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) to the regulatory
management of Waste Operations facilities in Australia. ARPANSA is the regulatory authority for Commonwealth entities
operating nuclear installations including radioactive waste operations facilities. In assessing the application for operating nuclear
installations the ARPANSA assessors prepare a Safety Evaluation Report which is a recommendation to the Chief Executive Officer
(CEO) of ARPANSA whether to issue a licence to site, construct, operate and decommission facilities. In particular the CEO
must take into account international best practice in radiation protection and nuclear safety when making licence decisions.
ARPANSAs integrated regulatory approach provides an effective framework to ensure that the Australian Nuclear Science and
Technology Organisation (ANSTO) Waste Operations facilities are operated in a safe manner.
SESSION 60 - L/ILW TREATMENT TECHNOLOGY DEVELOPMENT AND IMPLEMENTATION
1) A NEW APPROACH TO THE COMBINED CONDITIONING OF SOLID AND SLUDGE NUCLEAR WASTE - 16218
Lisa Hayes, Doug Kirk, BNES Nuclear Services (UK)
BNS Nuclear Services Limited has developed a novel process, the Versatile Encapsulation Plant (VEP) for the conditioning of
both solid waste and high solids sludge in a single plant. VEP uses mature technology and is independent of the container geometry.
<strong>The</strong> system is currently being proof of scale trialled against competing technologies as part of a Sellafield Project risk reduction
initiative.
In essence, VEP consists of the equipment necessary to receive sludge waste streams of either low or intermediate level,
remove excess water and concentrate the waste. It then adds a pre-mixed wet encapsulation medium, or grout, and transfers the
dewatered sludge and encapsulation medium into a static mixer mounted inside the container. <strong>The</strong> ‘mixed’ sludge and encapsulation
stream is deposited into a waste container of any shape, maximising storage efficiency for long-term storage/disposal. Since
there are no moving parts in the container, solid waste can be encapsulated with either ‘clean grout’ or a ‘sludge rich grout’ by the
same plant.
<strong>The</strong> technologies behind the development of VEP will explained in detail in this Paper, as will the rigorous testing process it
has undergone. Finally, potential future developments for VEP and the way in which it can be applied to meet the needs of nuclear
power plants around the world will be promulgated.
2) EXPERIENCE WITH OPERATION OF MOVABLE CEMENTATION FACILITY AT A1 NPP - 16038
Zuzana Holicka, Dusan Kevicky, Vladimir Michal, Marian Urbanec, VUJE, Inc., Trnava,Slovakia
<strong>The</strong> purpose of the paper is to describe a mobile cementation facility (MCF), which was designed by VUJE, Inc. and by
JAVYS, Inc. (Nuclear and Decommissioning Company) in 2003. MCF was constructed and installed in 2004 in the socalled garden
nearby A-1 NPP in Jaslovske Bohunice, where underground storage tanks for liquid radioactive waste are located. <strong>The</strong> facility
is designed to process liquid radioactive waste and sludge or gravel collected from the underground tanks.
<strong>The</strong>se storage tanks are situated in the vicinity of active water treatment plant belonging to A-1 NPP. <strong>The</strong> tanks, some of which
are of diameter 16 m, have their internal complex structure. All tanks were designed to collect various liquid waste streams from
the A-1 NPP reactor building. Special remotely controlled DENAR 41 manipulator was developed. for the collection of liquid waste
as well as for other purposes (collection of solid waste, decontamination, cutting of internal pipelines, etc.) <strong>The</strong> unique mobile
equipment, which carries a suitable pump for sludge pumping to the cementation facility, was used to collect sludge last year. Large
diameter of the storage tanks and small hatchways for the inspection access (approximately 540 x 540 mm) through which the telescopic
mast of manipulator DENAR 41 or the special mobile vehicle were inserted into the tanks proved to pose some difficulties
while being at use.
3) CONSTRUCTION AND OPERATION OF A MICROFILTRATION PLANT
FOR THE TREATMENT OF RADIOACTIVE WASTEWATER - 16019
Andreas Vesely, Herbert Trombitas; Nuclear Engineering Seibersdorf (Austria)
Design, construction and first operational experiences of a microfiltration plant for the treatment of radioactive wastewater are
presented. <strong>The</strong> plant shows excellent results regarding the removal of radionuclides from wastewater. In comparison to an existing
facility (co-precipitation of the radionuclides and filtration with a disk filter, operating with filter aid), the new plant generates
approximately one tenth of the amount of waste, and the use of chemicals is highly reduced.
4) NDAS GENERIC RESEARCH PROGRAMME FOR WASTE MANAGEMENT ISSUES - 16390
James McKinney, Nuclear Decommissioning Authority (UK)
NDA has a responsibility to ensure decommissioning activities are sufficiently technically underpinned and appropriate
Research and Development (R&D) is carried out. <strong>The</strong> NDA funds research and development (R&D) indirectly via the Site Licence
Companies (SLCs) or directly. <strong>The</strong> main component of directly funded R&D is the NDA Direct Research Portfolio (DRP). <strong>The</strong>
DRP is split into four framework areas:
• University Interactions
• Waste Processing
• Material Characterisation
• Actinide and Strategic Nuclear Materials
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Session 60-61 Abstracts
<strong>The</strong>se four framework areas were competed through an Official Journal of European Union (OJEU) process in 2008. Although
all four areas involve waste management, Waste Processing and Material Characterisation specifically deal with Higher Activity
Waste (HAW) waste management issues. <strong>The</strong> Waste Processing area was awarded to three groups: (i) National Nuclear Laboratory
(NNL), (ii) Consortium led by Hyder Consulting Ltd, and (iii) Consortium led by UKAEA Ltd. <strong>The</strong> Material Characterisation
area was awarded to three groups: (i) NNL, (ii) Serco, and (iii) Consortium led by UKAEA Ltd.
5) SIDE RADWASTE TREATMENT FACILITIES FOR THE WESTINGHOUSE AP1000 PROJECTS IN SANMEN
UND HAIYANG, PR CHINA - 16410
Andreas Roth, Hansa Projekt Anlagentechnik GmbH (Germany); John Merrell, Westinghouse Electric Co Uk Ltd (UK)
Currently two blocks of the Westinghouse AP1000 pressurized water-reactor are built at the sites Sanmen und Haiyang in the
Peoples Republic of China. 6-8 blocks of the reactor type will be operated during ultimate installation at each side.
<strong>The</strong> waste treatment concept in the US is orientated towards external conditioning service and therefore the Westinghouse plan
of concept for the AP1000 doesnt contain any other waste treatment facilities for waste beside the power plants water treatment.
Loading units for transport to external service providers are planned instead of that.
<strong>The</strong>re is no essential infrastructure of potential service providers in the PR China and therefore a coherent waste treatment concept
was needed for the building license.
Because of that Hansa Projekt Anlagentechnik GmbH developed a plan of concept for building waste treatment centers at the
different sides in cooperation with the Shanghai Nuclear Engineering and Design Institute.
6) STATISTICAL MODELLING APPLIED TO THE CONTENTS OF WASTE DRUMS - 16085
Richard Bull, Ian Pearman, Nuvia Limited (UK)
Gamma spectrometry is widely used to determine the radioactive content of waste drums. However, the results of such surveys
often result in large numbers of limit-of-detection (LOD) results. In this paper we will show how simple statistical methods can be
used to obtain useful information on the average drum activities, even in these unfavourable circumstances.
Results from measurements on 60Co, 152Eu, 154Eu activities in drums of waste from decommissioning of the GLEEP reactor
suggest that these activities are lognormally distributed with geometric standard deviations (GSD) ranging from 3-4. This statistical
model can be used to extract information from 235U, 234mPa and 234Th datasets which show only LOD activity results. In a
repository of N drums, each with activity

Abstracts Session 61
According to regulations, a number of design basis cases should be identified based on scenarios that can be shown to be especially
important from the standpoint of risk. A few such cases can be derived from the results of SKBs most recent safety assessment
SR-Can. <strong>The</strong>se cases also involve several assumptions on the state of other barriers.
2) CHARACTERIZATION OF A FE-BASED ALLOY SYSTEM FOR A AFCI METALLIC WASTEFORM - 16134
Mark Williamson, Savannah River National Lab (USA); Marie Kane, Savannah River National Laboratory (USA);
Bob Sindelar, Savannah River National Lab (USA)
<strong>The</strong> AFCI waste management program aims to provide a minimum volume stable waste form for high level radioactive waste
from the various process streams. <strong>The</strong> AFCI Integrated Waste Management Strategy document has identified a Fe-Zr metallic waste
form (MWF) as the baseline alloy for disposal of Tc metal, undissolved solids, and TRUEX fission product wastes. Several candidate
alloys have been fabricated using vacuum induction melting to investigate the limits of waste loading as a function of Fe and
Zr content. Additional melts have been produced to investigate source material composition. <strong>The</strong>se alloys have been characterized
using SEM/EDS and XRD. Phase assemblage and specie partitioning of Re metal (surrogate for Tc) and noble metal FP elements
into the phases is reported.
3) THE COLLABORATIVE EU PROJECT RECOSY - 16203
Bernhard Kienzler, Gunnar Buckau, Forschungszentrum Karlsruhe (Germany)
<strong>The</strong> Collaborative Project (CP) ReCosy (Redox Controlling Systems) was established in 2008. It falls within the EURATOM
program and is implemented within the European Commission’s 7th Framework Program. Main objectives of CP ReCosy are the
sound understanding of redox phenomena controlling the long-term release/retention of radionuclides in nuclear waste disposal and
providing tools to apply the results to Performance Assessment/Safety Case. Although redox is not a new geochemical problem,
different questions are still not resolved and thus raised by implementers and scientists. Radionuclide redox transformations on minerals
are considered to be decisive scenarios in various FEP lists.
32 institutions from 13 European countries contribute to the 4-years CP by i) development of advanced analytical tools, ii)
investigations of processes responsible for redox control (thermodynamically and kinetically controlled processes, surface reactions
and microbial processes), iii) provision of required data on redox controlling processes, and iv) response of the disposal systems to
external/internal disturbances. Systems which are investigated comprise simple very well defined ones under controlled laboratory
conditions, complex laboratory systems, near-natural systems in the laboratory, real systems, and near-field systems controlled
spent nuclear fuel.
4) MODELLING RADIONUCLIDE MOBILITY OF SPENT FUEL IN A DEEP
GEOLOGICAL REPOSITORY LOCATED IN A CLAY BEDROCK - 16240
Abel Tamayo, Lara Duro, Jordi Bruno, Amphos 21 (Spain);Aurora Martínez-Esparza, ENRESA (Spain)
Source term models are widely used to assess the behaviour of spent nuclear fuel after final disposal. However, most models
do not take into account some phenomena which are expected to control the transport of radionuclides through the near field. Some
uncertainties arise from this fact, thus making it difficult to obtain proper simulations of radionuclide behaviour in the near field.
In this work, we have used a compartmental code to built up an integrated source term model which overcomes the above-mentioned
drawbacks. Such model takes into account radiolytically-mediated matrix dissolution, radioactive decay chains, diffusive
transport, and retardation by sorption and secondary phase precipitation, among other processes. In addition, this model has been
used to estimate radionuclide mobility from spent fuel located in a conceptual clay geological repository.
5) EVALUATION OF MECHANICAL EFFECTS OF THE FAULT MOVEMENT ON
THE ENGINEERED BARRIER SYSTEM - 16269
Yuya Saito, Japan Atomic Energy Agency, (Japan); Mayuka Nishimura, Takashi Hirai, Takenaka Civil Engineering &
Construction Co., Ltd, (Japan); Kenji Tanai, Morimasa Naito, Japan Atomic Energy Agency (Japan)
Experiments and numerical analyses have been conducted to investigate the consequences of an active fault crosscutting the
engineered barrier system (EBS) of a high-level radioactive waste (HLW) repository. Experiments were performed using laboratory
simulation test equipment at a scale of 1:20, which can simulate the chosen shear displacements of 80 % and 140 % of the buffer
thickness, and the chosen shear rates of 0.1 m/s, 0.05 m/s and 0.01 m/s. <strong>The</strong> experiments have so far demonstrated that the metal
overpack will be rotated, but not breached, due to the plasticity of the surrounding bentonite buffer. <strong>The</strong> total pressure on the bentonite
buffer increases with an increase in the shear rate.
6) STUDY ON PERFORMANCE ASSESSMENT FOR HLW REPOSITORY IN CHINA - 16228
Weiming Chen, Ju Wang, Rui Su, Yunfeng Li, Beijing Research Institute of Uranium Geology (China)
This paper presents the latest achievements of performance assessment (PA) for high level radioactive waste (HLW) repository
in China. <strong>The</strong> first PA model, taking Beishan granite site as an example, is established with GoldSim and is verified by comparison
with Japanese PA model. <strong>The</strong>n the behaviors of granite repository in Beishan area are simulated. <strong>The</strong> results from these simulations
show that the engineered barrier is the most important part inside the repository, especially its bentonite plays a key role
in the retardation of repository after the nuclide is released from the vitrified waste. Five sensitive parameters are identified and two
design parameters are optimized. As a result, it has been proved that performance assessment model is a necessary tool to understand
the behaviors of repository, to identify sensitive parameters, and to optimize design parameters.
135

Session 62 Abstracts
SESSION 62 - RECENT DEVELOPMENTS IN ER TECHNOLOGIES
1) THE DEVELOPMENT OF METALLISED MEMBRANES FOR ANALYTICAL SEPARATION PROCESSES - 16069
Michael A Bromley, John Tyndall Institute for Nuclear Research (UK); Colin Boxall, University of Lancaster (UK);
Sarah Galea, John Tyndall Institute for Nuclear Research (UK);
Jonathan Francis, University of Central Lancashire (UK)
Fast, controllable and selective separation of metal ions from complex solutions plays a key role in a wide range of activities
including; chemical analysis, environmental monitoring, environmental remediation, metal recycling, desalination and process control,
to name but a few. <strong>The</strong>se activities are in turn encountered in a wide range of industries including; the nuclear, pharmaceutical,
mining, foodstuffs, power generation and wastewater processing industries.
Novel, surface-metallised, ion-selective membranes are being developed for use in the separation and preparation of pure isolates
of a range of metal ions prior to their analysis. Passage of ions through the membranes will be controlled by the application
of an electric field across the membrane. <strong>The</strong>se metallised membranes will to be used as the principle component of a suite of novel
methods for premeasurement separation and preconcentration of analytes of interest to the Nuclear Industry.
<strong>The</strong> membranes are metallised utilising semiconductor photocatalysis to initiate electroless deposition. <strong>The</strong> technique uses light
in place of a chemical catalyst. During absorption of light at or above the band-gap energy at the semiconductor, electrons are excited
from the valence band to the conduction band, creating electron/hole pairs. <strong>The</strong> photogenerated electrons are used to drive the
initial metal ion reduction reaction, resulting in the deposition of principle metal particles onto the semi-conductor surface, which
in turn, catalyse electroless deposition onto the surface.
2) CHARACTERIZATION OF CADMIUM-RESISTANT BACTERIA AND THEIR
APPLICATION FOR CADMIUM BIOREMEDIATION - 16072
Surasak Siripornadulsil, Wilailak Siripornadulsil, Khon Kaen University (Thailand)
On a global basis, trace-metal pollution is one of the most pervasive environmental problems. It is particularly difficult to prevent
or clean up because the metals are toxic in their elemental form and cannot be decomposed. Bioremediation has been shown
to be a powerful system for heavy metal pollution clean up and prevention. In this work, we characterized the cadmium (Cd)-resistant
bacteria isolated from rice field soil downstream from zinc (Zn) mineralized area which the owners were contaminated at high
level of cadmium content in their blood (>10 μgCd/g creatinine). We found that all 24 isolated bacteria tolerated toxic Cd concentrations
(2,500 μM). In order to determine whether the Cd toxicity affected the growth of isolated bacteria, we grew the isolated
bacterial cells in the absence and presence of toxic concentrations of CdCl2 (500 μM). In the absence of Cd, all isolated bacterial
cells grew slightly better than in the presence of toxic concentrations of Cd. In addition, the Cd binding capacity of all isolated bacteria
were very high, ranging from 6.38 to 9.38 log[Cd(atom)]/cell when grown in the presence of 500 μM CdCl2. Furthermore,
the stability of Cd-bacteria complex of all isolated bacteria was affected by 1mM EDTA.
When grown in the presence of 500 μM CdCl2, Cd-resistant isolates S2500-6, -8, -9, -15, -17, -18, -19, and -22
increasingly produced proteins containing cysteine (SH-group) (from 1.3 to 2.2 times) as well as 11 isolates of Cd-resistant
bacteria, including S2500-1, -2, -3, -5, -6, -8, -9, -11, -16, -20, and -21, increasingly produced inorganic sulfide (1.5 to 4.7 times).
Furthermore, the Sulfur K-edge X-ray absorption nearedge structure (XANES) spectroscopy studies indicated that Cd-resistant isolated
S2500-3 precipitated amounts of cadmium sulfide (CdS), when grown in the presence of 500 μM CdCl2. <strong>The</strong> results suggested
that these Cd-resistant bacteria have potential ability to precipitate a toxic soluble CdCl2 as nontoxic insoluble CdS. Interestingly,
Cd-resistant bacteria isolated S2500-3, -8, -9,and -20 increased cadmium tolerance of Thai jasmine rice (Kao Hom Mali 105)
when grown in the presence of 200 μM CdCl2. <strong>The</strong>se 4 isolates also decreased cadmium concentration accumulation in Kao Hom
Mali 105 plant at 61, 9, 6, and 17%, respectively when grown in the presence of 200 μM CdCl2. <strong>The</strong>y were identified by 16S rDNA
sequence analysis and classified as Cupriavidus taiwanensis (isolate S2500-3) and Pseudomonas aeruginosa (isolates S2500-8, -
9, and -20).
3) ENHANCED BIOREMEDIATION AS A COST EFFECTIVE APPROACH FOLLOWING
THERMALLY ENHANCED SOIL EXTRACTION FOR SITES REQUIRING REMEDIATION
OF CHLORINATED SOLVENTS - 16296
Anna-Maria Kozlowska, AIG Engineering Group Limited (UK);
Steve R. Langford, AIG Engineering Group Limited (UK); Dr H.G. Williams, EnviroGene Ltd (UK)
<strong>The</strong>rmally enhanced bioremediation can be a more cost-effective alternative to full-scale in-situ thermal treatment especially
for sites contaminated with chlorinated solvents, where reductive dechlorination is or might be a dominant biological step.
<strong>The</strong> effect of <strong>The</strong>rmally Enhanced Soil Vapour Extraction (TESVE) on indigenous microbial communities and the potential
for subsequent biological polishing of chlorinated solvents was investigated in field trials at the Western Storage Area (WSA) —
UKAEA — Oxfordshire, UK.
<strong>The</strong> WSA site had been contaminated with various chemicals including mineral oil, chloroform, trichloroethane (TCA), carbon
tetrachloride and tetrachloroethene (PCE). <strong>The</strong> contamination had affected the unsaturated zone, groundwater in the chalk
aquifer and was a continuing source of groundwater contamination below WSA.
During TESVE the target treatment zone was heated up above the boiling point of water increasing the volatalization degree
of contaminants of concern (CoC), which were mobilised and extracted in the vapour phase. A significant reduction of chlorinated
solvent in the unsaturated zone was achieved by a full-scale application of TESVE In Situ <strong>The</strong>rmal Desorption (ISTD) technology.
136

Abstracts Session 62-63
4) BIOAVAILABILITY OF MERCURY IN CONTAMINATED OAK RIDGE WATERSHED AND POTENTIAL
REMEDIATION OF RIVER/RUNOFF/STORM WATER BY AN AQUATIC PLANT - 16319
Yi Su, Fengxiang X. Han, Jian Chen, Yunju Xia, David L. Monts, Mississippi State University (USA)
Historically as part of its national security mission, the U.S. Department of Energys Y-12 National Security Facility in Oak
Ridge, TN, USA acquired a significant fraction of the worlds supply of elemental mercury. During the 1950s and 1960s, a large
amount of elemental mercury escaped confinement and is still present in the buildings and grounds of the Y-12 Facility and in the
Y-12 Watershed. Because of the adverse effects of elemental mercury and mercury compounds upon human health, the Oak Ridge
Site is engaged in an on-going effort to monitor and remediate the area. <strong>The</strong> main thrust of the Oak Ridge mercury remediation
effort is currently scheduled for implementation in FY09. In order to more cost effectively implement those extensive remediation
efforts, it is necessary now to obtain an improved understanding of the role that mercury and mercury compounds play in the Oak
Ridge ecosystem.
Most recently, concentrations of both total mercury and methylmercury in fish and water of lower East Fork Poplar Creek
(LEFPC) of Oak Ridge increased although the majority of mercury in the site is mercury sulfide. This drives the US DOE and the
Oak Ridge Site to study the long-term bioavailability of mercury and speciation at the site. <strong>The</strong> stability and bioavailability of mercury
sulfide as affected by various biogeochemical conditions presence of iron oxides have been studied. We examined the kinetic
rate of dissolution of cinnabar from Oak Ridge soils and possible mechanisms and pathways in triggering the most recent increase
of mercury solubility, bioavailability and mobility in Oak Ridge site. <strong>The</strong> effects of pH and chlorine on oxidative dissolution of
cinnabar from cinnabar-contaminated Oak Ridge soils will be discussed.
On the other hand, aquatic plants might be good candidate for phytoremediate contaminated waste water and phytofiltration of
collective storm water and surface runoff and river. Our greenhouse studies on uptake of Hg by water lettuce (Pistia stratiotes) show
that water lettuce is effectively removing Hg from water solution and Hg was mostly stored in roots. One day of growing could
remove 93-98% of Hg from water solutions. However, Hg shows acute toxicity to water lettuce as indicated by decreases in fresh
biomass and moisture contents.
5) REMEDIATION OF URANIUM- AND CHC-CONTAMINATED GROUNDWATER
ON A FORMER NUCLEAR FUEL-ELEMENT PRODUCTION SITE - 16244
Joerg Woerner, Sonja Margraf, RD Hanau (Germany)
Since July 2002 a pump & treat remedial action has been in operation for the extraction of Uranium- and CHC-compoundscontaminated
ground-water flowing below an industrial area used before as production site for nuclear fuel elements. So far about 17
kg Uranium and 22 kg CHC-compounds have been eliminated. As described earlier [1] two ground-water plumes have transported
the Uranium down-stream to locations where two main remediation wells are placed. <strong>The</strong>y show characteristic differences with
respect to their Uranium-nuclide vector. More than 220.000 m³ ground-water of the whole 350.000 m³ have been pumped therefrom.
Preferred ground-water paths cause blending the two plumes waters. <strong>The</strong> first plumes water characterized by decreasing Uranium-235
ratios is meanwhile dominated by the second plumes water of up to 85% in case of well W10. <strong>The</strong> overall activity of 122
MBq Uranium-235 has been extracted from the saturated zone with decreasing quantities. Only a small area remains where the first
plumes pure ground water will be extracted in future. Both target values of 20 ?g/l and 10 ?g/l for dissolved Uranium and CHCcompounds,
respectively, could not yet be reached for all remediation wells. In accordance to the 10?Sv-concept of radiation protection
the improvement of specific parameters will still be necessary in order
SESSION 63 - NATURAL ANALOGUES IN RADWASTE DISPOSAL - ANSWERING THE HARD QUESTIONS
1) IMPLICATIONS OF MICROBIAL REDOX CATALYSIS IN ANALOGUE SYSTEMS
FOR REPOSITORY SAFETY CASES - 16336
Julia M West, British Geological Survey (UK); Ian McKinley, McKinley Consulting (Switzerland);
Simcha Stroes-Gascoyne, AECL, Whiteshell Laboratories (Canada)
A detailed assessment of studies of oxidising redox fronts around fractures at depth in otherwise reducingenvironments suggests
that the usual explanation in terms of disturbances that have, in the past, resulted in deep penetration of oxidising water are
incompatible with observations. An alternative hypothesis involving microbial catalysis of kinetically hindered reactions involving
oxyanions such as sulphate or carbonate appears potentially more credible. Although still not always taken into account by the geochemical
community, the role of microbial metabolism on subsurface geochemistry is supported by the rapidly expanding database
on subsurface microbial populations. <strong>The</strong>se populations are demonstrated to be viable and, therefore, could potentially be active at
levels close to or below current detection limits (either continuously or intermittently) in deep geological systems. Indeed, inspection
of information available from several analogue studies or repository site characterisation programmes suggests that such activity
may explain some of the geochemical anomalies encountered.
This paper examines the current (indirect) evidence for microbial redox catalysis in relevant subsurface environments and considers
the implications that this would have for the development of site understanding and, in particular, the identification of factors
that may distinguish between different locations during site selection. Further, it examines the wider implications of more
extensive roles of microbes in repository systems on the overall post-closure safety case and the need for further focused analogue
studies to develop answers to these open questions.
137

Session 63 Abstracts
2) ALTERED CRYSTALLINE ROCK DISTRIBUTED ALONG GROUNDWATER CONDUCTIVE FRACTURES
AND THE RETARDATION CAPACITY IN THE OROGENIC FIELD OF JAPAN - 16332
Yoshida Hidekazu, Nishimoto Shoji, Nagoya University (Japan);
Richard Metacalfe, Quintessa (UK)
In the orogenic field Japanese islands, there are wide areas of crystalline rocks that inevitably contain groundwater conductive
fractures associated with alteration zones. However, little attention has been given to the formation process and possible influence
on the radionuclides migration from radioactive waste repository that might be sited within crystalline rock. In particular, the influences
of alteration minerals and microfractures, due to chemical sorption and/or physical retardation are required to assess the realistic
barrier function. In order to understand the alteration process and the retardation capacity, detailed mineralogical and physicochemical
characterization of altered crystalline rocks have been carried out. Mineralogical analysis reveals that the altered crystalline
rocks have been formed through basically two stages of water-rock interaction during and after uplift. Physico-chemical
characteristics including laboratory sorption experiments show that altered crystalline rock has a certain volume of accessible
porosity, particularly in plagioclase grains, which would influence on nuclide retardation more than the accessible porosity in other
minerals present, such as biotite. <strong>The</strong>se results provide confidence that even altered and fractured parts of any crystalline rock that
might be encountered in a site for the disposal of high-level radioactive waste may still play a role of barrier function.
3) GEOCHEMICAL BEHAVIOUR OF URANIUM IN SEDIMENTARY FORMATIONS:
INSIGHTS FROM A NATURAL ANALOGUE STUDY - 16340
Ulrich Noseck, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mb (Germany); Juhani Suksi, Helsinki
University (Finland); Vaclava Havlova, Radek Cervinka, Nuclear Research Institute Rez plc. (Czech Republic);
Thomas Brasser, GRS Braunschweig (Germany)
Groundwater data from the natural analogue site Ruprechtov have been evaluated with special emphasis on the uranium behaviour
in the so-called uranium-rich clay/lignite horizon. In this horizon in-situ Eh-values in the range of -160 to -280 mV seem to be
determined by the SO42-/HS- couple. Under these conditions U(IV) is expected to be the preferential redox state in solution. However,
on-site measurements in groundwater from the clay/lignite horizon show only a fraction of about 20 % occurring in the
reduced state U(IV). <strong>The</strong>rmodynamic calculations reveal that the high CO2 partial pressure in the clay/lignite horizon can stabilise
hexavalent uranium, which explains the occurrence of U(VI). <strong>The</strong> calculations also indicate that the low uranium concentrations in
the range between 0.2 and 2.1μg/l are controlled by amorphous UO2 and/or the U(IV) phosphate mineral ningyoite. This confirms
the findings from previous work that the uranium (IV) mineral phases are long-term stable under the reducing conditions in the
clay/lignite horizon without any signatures for uranium mobilisation. It supports the current knowledge of the geological development
of the site and is also another important indication for the long-term stability of the sedimentary system itself, namely of the
reducing geochemical conditions in the near-surface (30m to 60 m deep) clay/lignite horizon. Further work with respect to the
impact of changes in redox conditions on the uranium speciation is on the way.
4) THE RUPRECHTOV NATURAL ANALOGUE SITE (CZ) STUDY: MOBILE NATURAL ORGANIC MATTER
IDENIFICATION, CHARACTERIZATION AND LINK TO PA RELEVANT PROCESSES - 16341
Vaclava Havlova, Nuclear Research Institute Rez plc. (Czech Republic); Ulrich Noseck, Gesellschaft für Anlagen- und
Reaktorsicherheit (GRS) mbH (Germany); Radek Cervinka, Nuclear Research Institute Rez plc. (Czech Republic);
Thomas Brasser, GRS Braunschweig (Germany); Josef Havel, Masaryk University (Czech Republic)
<strong>The</strong> Ruprechtov Natural Analogue (CZ) Programme has been focused on studying real system processes, relevant to performance
assessment (PA) of sediment formations that can form the overburden of geological repository host rocks. <strong>The</strong> site has been
extensively studied due to its geological constitution (granite kaolin clay U mineralisation organic matter).
<strong>The</strong> presented study used Ruprechtov unique, but well-described geological conditions in order to identify and characterise
mobile organic matter (MOM) that can be easily released into groundwater and can influence PA relevant specie migration due to
complexation/sorption reaction. <strong>The</strong> modern analytical method MALDI-TOF MS was used for characterisation. It was found that
only a small fraction of sedimentary natural organic matter (NOM) from the site was easily releasable (max. 5%) as MOM, resulting
in low organic substance concentration in natural groundwater. MOM amount released was decreasing with increasing NOM
content.
MALDI-TOF MS proved to be a useful tool to characterize organic substances, either natural ones or artificially released from
natural organic matter samples. A noticeable fingerprint for all the MOM compounds analysed was found at MALDI-TOF MS spectra.
This showed that MOM from the Ruprechtov site was in all cases composed of molecules with low molecular weight (under
1000 Da). As determined by the consequent geochemical analyses, despite groundwater reducing conditions MOM compounds
would be mainly interacting with U(VI) in the groundwater, being present as more abundant U specie. Good correspondence of
results enabled to consider the extracted humic acid HA 12/3 as a mobile organic matter fraction representative.
5) THE ARCHAEOLOGICAL ANALOGUE APPROACHES TO PREDICT THE LONG TERM CORROSION
BEHAVIOUR OF CARBON STEEL OVERPACK AND REINFORCED CONCRETE STRUCTURES
IN THE FRENCH DISPOSAL SYSTEMS - 16343
Delphine Neff, CEA (France); Mandana Saheb, CEA/ANDRA (France); Judith Monnier, CNRS (France); Solenn
REGUER, Synchrotron SOLEIL (France); Walter Chitty, AREVA (France); Stéphane Perrin, Michael Descostes, Valérie
L’Hostis, CEA (France); Didier Crusset, ANDRA (France); Philippe Dillmann, CNRS (France)
<strong>The</strong> aim of this paper is to give an overview of several years of research on archaeological analogues, strongly connected with
other approaches in order to predict the long term behaviour of the steel canister or the concrete structure. It aims at showing the
specific methodology and the complementarities of the different approaches. First reference archaeological sites on which on field
measurement can be performed and a significant number of artefact selected for study. Second, artefact are finely characterized
combining several microbeam chemical and structural methods. <strong>The</strong>n corrosion mechanisms hypotheses are tested using specific
isotopic markers for re corroding experiments. Finally specific parameters for the model can be gathered. <strong>The</strong> paper also aims at
presenting the new research perspectives and challenges for the next future.
138

Abstracts Session 63
6) FORMATION OF SECONDARY MINERALS AND UPTAKE OF VARIOUS ANIONS UNDER NATURALLY-
OCCURRING HYPERALKALINE CONDITIONS IN OMAN -16344
Sohtaro Anraku, Tsukuba Sato, Tetsuro Yoneda, Hokkaido University (Japan);
Kazuya MORIMOTO, National Institute for Materials Science (Japan)
In Japanese transuranic (TRU) waste disposal facilities, 129I is the most important key nuclide for the long-term safety assessment.
Thus, the Kd values of I to natural minerals are important factor in the safety assessment. However, the degradation of cement
materials in the repositories can produce high pH pore fluid which can affect the anion transport behavior. <strong>The</strong>refore, it is necessary
to understand the behavior of anions such as I- under the hyperalkaline conditions.
<strong>The</strong> natural hyperalkaline spring water (pH>11) in the Oman ophiolite is known to be generated from the partly serpentinized
peridotites. <strong>The</strong> spring water is characteristically hyperalkaline, reducing, low-Mg, Si and HCO3- , and high-Ca, while the river
water is moderately alkaline, oxidizing, high-Mg and HCO3-. <strong>The</strong> mixing of these spring and river water resulted in the formation
of secondary minerals. In the present study, the naturally occurring hyperalkaline conditions near the springs in Oman were used
as natural analogue for the interaction between cement pore fluid and natural Mg-HCO3- groundwater. <strong>The</strong> present aim of this paper
is to examine the conditions of secondary mineral formation and the anion uptake capacity of these mineral in this system.
Water and precipitate samples were collected from the different locations around the spring vent to identify the effect of mixing
ratios between spring and river water on mineral composition and water-mineral distribution coefficient of various anions. Onsite
synthesis was also carried out to support these data quantitatively.
Aragonite was observed in all precipitates, while calcite, brucite and Mg-Al hydrotalcite-like compounds (HTlc) were also
determined in some samples. Calcite was observed only closed to the springs. At locations far from the springs, calcite formation
was inhibited due to high-Mg fluid from river water. Brucite was observed from the springs with relatively low-Al concentration
and HTlc was the opposite.
During the formation of the minerals at the mixing points, HCO3- in the river water was fixed as carbonate minerals such as
in aragonite and calcite while H3SiO4- in the river water was dominantly fixed into interlayers and surfaces of HTlc. Iodine in spring
and river water was mainly fixed in aragonite. <strong>The</strong>refore, the uptake I- by secondary minerals can be expected at hyperalkaline conditions
as observed at Oman hyperalkaline springs.
7) REACTION OF BENTONITE IN LOW ALKALI CEMENT LEACHATES: PRELIMINARY RESULTS
FROM THE CYPRUS NATURAL ANALOGUE PROJECT (CNAP) - 16276
W. Russell Alexander, Bedrock Geosciences (Switzerland)
Bentonite is a key component in many designs for radioactive waste repositories. <strong>The</strong> plasticity, swelling capacity, colloid filtration,
low hydraulic conductivity, high retardation of key radionuclides and stability in relevant geological environments all make
bentonite an ideal barrier/buffer material. However, bentonite is chemically unstable under higher pH conditions and this is a potential
problem for repository designs which mix cement and concrete with bentonite barriers. <strong>The</strong> hyperalkaline (pH~13) leachates
from the cement are expected to cause alteration of the bentonite. Low alkali cements produce lower pH (around 10-11) leachates
and it is expected that this will slow bentonite reaction (or even stop it altogether) over the timespan of relevance to repository safety.
Unfortunately, it has proven extremely difficult to study these very slow reactions in the laboratory so an alternative approach,
that of studying natural analogues of the reaction process, has begun in Cyprus. In this paper, preliminary details of this new investigation
of long-term bentonite reaction in the natural hyperalkaline groundwaters of the Troodos ophiolite in Cyprus are presented.
Here, groundwater pH values of 10.0 to 11.9 have been reported, falling into the range typical of low-alkali cements that are
presently being developed for use in radioactive waste disposal. <strong>The</strong> aims of this stage of the project were to identify likely sites of
hyperalkaline groundwater/bentonite reaction and assess the relevance of the current site conceptual model. Preliminary groundwater
and petrographic data for one group of related sites where...
8) DEVELOPMENTS IN HYPERALKALINE NATURAL ANALOGUE STUDIES
AROUND THE ZAMBALES OPHIOLITE, PHILIPPINES - 16278
C. Pascua, M. L.L. Honrado, University of Philippines (Philippines);
W. Russell Alexander, Bedrock Geosciences (Switzerland); Yamakawa, N. Fujii, RWMC (Japan);
K. Namiki, K. Kawamurs, Obayashi Corpration (Japan); I.G. McKinley, McKinley Consulting (Switzerland)
Past studies have identified ophiolites as potential sources of hyperalkaline waters that can be considered analogues of the
leachates produced by cementitious materials in repositories for radioactive waste. <strong>The</strong> Zambales ophiolite in the Philippines has
been determined to undergo widespread active serpentinisation, resulting in hyperalkaline springs at several locations. Measured
pH values range up to 11.1, falling into the range typical of low alkali cements that are presently being developed to minimise geochemical
perturbations resulting from use of concrete. A key goal is to examine the alteration of natural bentonite in contact with
such waters to determine if, indeed, pH values in this lower range eliminate the problems seen at the high values (>12) associated
with conventional concretes.
Evidence has been accumulated to support the conceptual model of hyperalkaline groundwater flow in fractures underlying
bentonite deposits in the Mangatarem area of the Zambales ophiolite. Drilling and trenching has exposed a direct contact between
bentonite and pillow lavas of the ophiolite and several generations of hyperalkaline groundwater flow within fracture zones have
been identified. As yet, water samples have not been obtained from this contact, but analysis of reacted bentonite is ongoing. Preliminary
data are reported here for the first time.
139

140
Pre-Registered Attendees by Country
Goyal, Kapil LOS ALAMOS NATIONAL LABS Albania
Miller, Charles U.S. NUCLEAR REGULATORY Andorra
COMMISSION
Drace, Zoran IAEA Austria
Hillebrand, Guenter NUCLEAR ENGINEERING Austria
Laraia, Michele IAEA Austria
Vesely, Andreas NUCLEAR ENGINEERING SEIBERSDORF Austria
Cuchet, Jean-Marie BELGONUCLEAIRE Belgium
Fransen, Ivo BELOGOPROCESS N.V Belgium
Luycx, Paul CASTER CONSULTING Belgium
Ooms, Bart BELGOPROCESS Belgium
Perko, Janez SCK CEN Belgium
Radohhe, Tanguy TRACTEBEL ENGINEERING Belgium
Simenon, Ronny NIRAS/ONDRAF Belgium
Steinkuhler, Claude DDR CONSULT Belgium
Vanderperre, Serge TRACTEBEL ENGINEERING Belgium
Brooks, Sheila ATOMIC ENERGY OF CANADA Canada
Fitzpatrick, Jonathan ATOMIC ENERGY OF CANADA Canada
Gechikov, Mark AMEC NSS Canada
Husain, Aamir KINECTRICS INC Canada
Kerwin, Richard GLOBAL PARTNERSHIP Canada
PROGRAMME (IGX)
Krasznai, John KINECTRICS INC Canada
Metcalfe, Doug NATURAL RESOURCES CANADA Canada
Muldoon, Joe SASKATCHEWAN RESEARCH COUNCIL Canada
Schramm, Laurier SASKATCHEWAN RESEARCH COUNCIL Canada
Sedor, Kelly NUCLEAR WASTE MANAGEMENT Canada
ORGANIZATION
Stepanik, Terry ATOMIC ENERGY OF CANADA Canada
Sykes, Jon UNIVERSITY OF WATERLOO Canada
Washer, Michael FOREIGN AFFAIRS & Canada
INTERNATIONAL TRADE CANADA
Havlova, Vaclava NUCLEAR RESEARCH INST. REZ PLC Czech
Republic
Harjula, Risto HELSINKI UNIVERSITY Finland
Paajanen, Airi UNIVERSITY OF HELSINKI Finland
Palmu, Marjatta POSIVA OY Finland
Tusa, Esko FORTUM NUCLEAR SERVICES Ltd Finland
Asou, Marielle COMMISSARIAT A L’ENERGIE France
ATOMIQUE
Barre, Yves COMMISSARIAT À L’ENERGIE France
ATOMIQUE
Butez, Marc CEA France
Fares, Toby ATOMIS ENERGY COMMISSION (CEA) France
Ferrus, Joel URS FRANCE France
Glorennec, Christian EDF France
Hornung, Frederic COMMISSARIAT A L’ENERGIE France
ATOMIQUE
Jeanjacques, Michel COMMISSARIAT À L’ENERGIE France
ATOMIQUE
Vuillier, Stephane SGN AREVAS GROUP France
Aymanns, Katharina FORSCHUNGSZENTRUM JÜLICH GMBH Germany
Becker, Dirk-Alexander GRS MBH Germany
Borchardt, Ralf ENERGIEWESHE NOID GMBH Germany
Eichhorn, Heiko NUKEM TECHNOLOGIES GMBH Germany
Fachinger, Johannes FURNACES NUCLEAR APPLICATIONS Germany
Geiser, Heinz GNS GESELLSCHAFT F NUCLEAR Germany
SERVICE MBH
Graf, Reinhold GNS MBH Germany
Gruendler, Detlef ISTEC Germany
Hafen, Hubert WÄLISCHMILLER ENGINEERING GMBH Germany
Haverkamp, Bernt DBE TECHNOLOGY GMBH Germany
Jakusz, Susann HANSA PROJEKT ANLAGENTECHNIK Germany
GMBH
Kienzler, Bernhard FORSCHUNGSZENTRUM KARLSRUHE Germany
Krone, Jürgen DBE TECHNOLOGY GMBH Germany
Kugel, Karin FEDERAL OFFICE FOR RADIATION Germany
PROTECTION
Noseck, Ulrich GRS MBH Germany
Posnatzki, Britta TUEV NORD ENSYS HANOVER GMBH Germany
& CO KG
Reich, Claudia WÄLISCHMILLER ENGINEERING GMBH Germany
Richter, Anke FZ DRESDEN ROSSENDORF Germany
Rieger, Ulrich FEDERAL MINISTRY OF ECONOMICS Germany
& TECHNOLOGY
Roth, Andreas HANSA PROJEKT ANLAGENTECHNIK Germany
GMBH
Scheffler, Beate NUKEM TECHNOLOGIES GMBH Germany
Schwall, Sebastian FORSCHUNGSZENTRUM JÜLICH GMBH Germany
Sokcic-Kostic, Marina NUKEM TECHNOLOGIES GMBH Germany
Stockmann, Madlen FZ DRESDEN ROSSENDORF Germany
Strelzig, Maja TUEV NORD ENSYS HANOVER Germany
GMBH & CO KG
Viermann, Jörg GNS GESELLSCHAFT F NUCLEAR Germany
SERVICE MBH
Weil, Leopold FEDERAL OFFICE FOR RADIATION
PROTECTION
Woerner, Jörg RD HANAU Germany
Zielonka, Holger TUEV NORD ENSYS HANOVER Germany
GMBH & CO KG
Antus, Andrea PAKS NUCLEAR POWER PLANT LTD Hungary
Berta, Zsolt MECSEK-ÖKO CO Hungary
CsQvári, Mihaly MECSEK-ÖKO CO Hungary
Elter, EnikQ PAKS NUCLEAR POWER PLANT LTD Hungary
Földing, Gabor MECSEK-ÖKO CO Hungary
Fritz, Laszlo PUBLIC LIMITED COMPANY FOR Hungary
RADIOACTIVE WASTE MAN.
Kapitany, Sandor PUBLIC LIMITED COMPANY FOR Hungary
RADIOACTIVE WASTE MAN.
Takats, Ferenc GOLDER ASSOCIATES HUNGARY Hungary
Misra, Shri BHABHA ATOMIC RESEARCH CENTRE India
Cadini, Francesco POLITECNICO DI MILANO Italy
Mingrone, Giorgio SOGIN SPA Italy
Zorzoli, Franco CAMPOVERDE SRL Italy
Amamoto, Ippei JAPAN ATOMIC ENERGY AGENCY Japan
Anraku, Sohtaro HOKKAIDO UNIVERSITY Japan
Iguchi, Yukihiro JAPAN NUCLEAR ENERGY SAFETY Japan
ORGANISATION
Ishii, Nobuyoshi NATIONAL INSTITUTE OF Japan
RADIOLOGICAL SCIENCES
Ishikura, Takeshi THE INSTITUTE OF APPLIED ENERGY Japan
Kitamura, Koichi JAPAN ATOMIC ENERGY AGENCY Japan
Makino, Hitoshi JAPAN ATOMIC ENERGY AGENCY Japan
Mimura, Hitoshi TOHOKU UNIVERSITY Japan
Mukunoki, Atsushi JGC CORPORATION Japan
Nishimoto, Shoji NAGOYA CITY SCIENCE MUSEUM Japan
Ohno, Shintaro KAJIMA CORPORATION Japan
Osawa, Hideaki JAPAN ATOMIC ENERGY AGENCY Japan
Sasaki, Michiya CRIEPI Japan
Semba, Takeshi JAPAN ATOMIC ENERGY AGENCY Japan
Shimada, Taro JAPAN ATOMIC ENERGY AGENCY Japan
Umeki, Hiroyuki JAEA Japan
Yoshida, Hidekazu NAGOYA UNIVERSITY Japan
Poskas, Povilas LITHUANIAN ENERGY INSTITUE Lithuania
Codée, Hans COVRA Netherlands
De Vos, Renate NRG Netherlands
Van Velzen, Leo NUCLEAR RESEARCH & Netherlands
CONSULTANCY GROUP
Verhoef, Ewoud COVRA N.V Netherlands
Welbergen, Jeroen COVRA Netherlands
Goldsworthy, Martin GOLDER ASSOCIATES Peru
Adina, Sandru SC MATE-FIN SRI Romania
Teodorov, Gabriela SC MATE_FIN SRI Romania
Toro, Laszlo SC MATE_FIN SRI Romania
Kozyrev, Denis RADIOACTIVE WASTE Russia
MANAGEMENT ENTERPRISE
Kulikov, Konstantin NIPTB ONEGA Russia
Maltsev, Alexey JSC Russia
Popov, Dmitry RADIOACTIVE WASTE Russia
MANAGEMENT ENTERPRISE
Sim, Eunice DSO NATIONAL LABORATORIES Singapore
Panik, Michal SLOVAK UNIVERSITY OF TECHNOLOGY Slovakia
Zachar, Matej SLOVAK UNIVERSITY OF TECHNOLOGY Slovakia
Virsek, Sandi ARAO Slovania
Fabjan, Marija AGENCY FOR RADWASTE MANAGEMENT Slovenia
Hertl, Bojan AGENCY FOR RADWASTE MANAGEMENT Slovenia
Kralj, Metka AGENCY FOR RADWASTE MANAGEMENT Slovenia
Cha, Jeonghun KAERI S Korea
Song, Myung-Jae DOOSAN HEAVY INDUSTRIES & S Korea
CONSTRUCTION
Duro, Lara AMPHOS 21 Spain
Lara, Esperanza CIEMAT Spain
Millan, Miguel WESTINGHOUSE Spain

Pre-Registered Attendees by Country
Andersson, Johan JA STREAMFLOW AB Sweden
Carlsson, Jan SKB Sweden
Eng, Torsten SKB Sweden
Källström, Klas SVENSK KÄRNBRÄNSLEHANTERING AB Sweden
Lindskog, Staffan SSM Sweden
Martensson, Per SWEDISH NUCLEAR FUEL & Sweden
WASTE MANAGEMENT CO
Sjöblom, Rolf TEKEDO AB Sweden
Stenmark, Anders STUDSVIK NUCLEAR AB Sweden
Torstenfelt, Börje SWEDISH NUCLEAR FUEL & Sweden
WASTE MANAGEMENT CO
Turner, Roland SWEDISH RADIATION SAFETY Sweden
AUTHORITY
Alexander, Russell BEDROCK GEOSCIENCES Switzerland
Ehrlicher, Ulrich PSA Switzerland
Gaus, Irina NAGRA Switzerland
McCombie, Charles ARIUS ASSOCIATION Switzerland
McKinley, Ian MCKINLEY CONSULTING Switzerland
Schneider, Jürg NAGRA Switzerland
Schumann, Dorothea PAUL SCHERRER INSTITUTE Switzerland
Vomvoris, Efstratios NAGRA Switzerland
Lai, Hung-Chih FCMA Taiwan
Siripornadulsil, Wilailak Khon Kean University Thiland
Siripornadulsil, Surasak Khon Kean University Thiland
Clark, Anna NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Clark, Matthew NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Craze, Andrew NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Davies, Phil NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Hughes, Lisa NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Hunt, Stuart NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
McKinney, James NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
McMinn, Mervin NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Rendell, Philip NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Touhey, Malcolm INTERNATIONAL NUCLEAR SERVICES UK
Wareing, Mark NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Adamson, David SELLAFIELD LTD UK
Adebanjo, Ayotunde SELLAFIELD LTD UK
Akhtar, Shuaib TESSELLA UK
Alderson, Ian NUCLEAR TECHNOLOGIES PLC UK
Alexander, Ellie ATKINS UK
Amos, Sean AWE PLC UK
Anderton, Bill NUCLEAR MANAGEMENT PARTNERS UK
Andrieux, Fabrice LANCASTER UNIVERSITY UK
Antrobus, Julianne NUVIA LIMITED UK
Arnold, David HALLIN ROBOTICS LTD UK
Askew, Graeme SELLAFIELD LTD UK
Astrop, Amanda STUDSVIK UK UK
Atyeo, Paul RSRL UK
Bacon, Michael HEALTH & SAFETY EXECUTIVE UK
Baines, Kim RSK RADIOLOGICAL UK
Bakari, Mohamed LANCASTER UNIVERSITY UK
Baker, Andrew ANDY BAKER CONSULTING UK
Baker, Jonathan CH2M HILL UK
Ball, John NUVIA LIMITED UK
Banford, Anthony NATIONAL NUCLEAR LABORATORY UK
Bartlett, Angela UKAEA UK
Bath, Adrian INTELLISCI LTD UK
Beadle, Ian AMEC UK
Bentley, Martin SELLAFIELD LTD UK
Berry, Robert FOXFIRE SCIENTIFIC INC UK
Biggs, Simon UNIVERSITY OF LEEDS UK
Blackmore, Jonathan RSRL UK
Bleasdale, Peter WASTE MANAGEMENT TECHNOLOGY UK
Blundell, Neil HEALTH & SAFETY EXECUTIVE UK
Boath, David AMEC UK
Bolton, Gary INDUSTRIAL TOMOGRAPHY SYSTEMS UK
Booth, Clare SELLAFIELD LTD UK
Booth, Peter NNL LTD UK
Boxall, Colin LANCASTER UNIVERSITY UK
Broadbent, Craig STUDSVIK UK UK
Bromley, Michael LANCASTER UNIVERSITY UK
Brookes, Christopher SELLAFIELD LTD UK
Browning, Stephen NUCLEAR TECHNOLOGIES PLC UK
Bruce, Georgina SELLAFIELD LTD UK
Bull, Richard NUVIA LIMITED UK
Burgess, Pete NUVIA LIMITED UK
Burke, Stephen NUCLEAR TECHNOLOGIES PLC UK
Burns, Kevin SELLAFIELD LTD UK
Butter, Kevin WASTE MANAGEMENT TECHNOLOGY UK
Cabrera, David MAGNOX NORTH UK
Campbell, Colin SELLAFIELD LTD UK
Campbell, Graham NUCLEAR MANAGEMENT PARTNERS UK
Candy, Simon SELLAFIELD LTD UK
Cane, Vince NUCLEAR TECHNOLOGIES PLC UK
Carrick, Jim URS WASHINGTON DIVISION UK
Case, Keith SELLAFIELD LTD UK
Cassidy, Helen SELLAFIELD LTD UK
Cassidy, James FATHOMS UK
Caunt, John JCS UK
Chadwick, Dominic UNIVERSITY OF MANCHESTER UK
Cheek, John SIEMPELKAMP NUCLEAR TECHNOLOGY UK
Chiba, Tamotsu JGC CORPORATION UK
Chorley, Gary SELLAFIELD LTD UK
Christie, Dylan NRG UK
Clark, Peter VT NUCLEAR SERVICES UK
Cochrane, Jim SEPA UK
Connolly, Mike IDAHO NATIONAL LABORATORY UK
Conroy, Julie MAGNOX NORTH UK
Cook, Laurence SELLAFIELD LTD UK
Cooper, John NUCLEAR ENGINEERING SERVICES LTD UK
Coppins, Gavin UKAEA UK
Crossland, Ian CROSSLAND CONSULTING UK
Cunningham, Bernard BIRSE NUCLEAR UK
Currie, Ian AMEC UK
Curry, Daniel URS CORPORATION UK
Darroch, Norman BABCOCK MARINE UK
Davey, Richard SELLAFIELD LTD UK
Davies, Tim UKAEA UK
De la Gardie, Fredrik SKB UK
De Sanctis, Jacopo POLITECNICO DI MILANO UK
Dean, Julian NATIONAL PHYSICAL LABORATORY UK
Deehan, Connor ATKINS LTD UK
Deeran, Paul FRASHER-NASH CONSULTANTS UK
Delaney, Brian HEALTH & SAFETY EXECUTIVE UK
Dodd, Kevin STUDSVIK UK UK
Drulia, Mark ENERGYSOLUTIONS UK
Duncan, Paul SCIENTIFICS LTD UK
Dux, Joachim WAK GMBH UK
D’vaz, Mark SELLAFIELD LTD UK
Edmiston, Lindsay NATIONAL NUCLEAR LABORATORY UK
Ehamparadasan, Raveenth PARSONS BRINCKERHOFF UK
Emptage, Matthew ENVIRONMENT AGENCY UK
Fairweather, Michael UNIVERSITY OF LEEDS UK
Fowler, Julian TESSELLA UK
Fretwell, Rod JORDAN NULCEAR UK
George, David URS UK
Gibson, Keith LLW REPOSITORY UK
Gifford-Nash, Tim MAGNOX SOUTH LTD UK
Giroir, Bob MAGNOX NORTH LTD UK
Gleason, Gene NAC INTERNATIONAL UK
Glover, Alec SELLAFIELD LTD UK
Grundy, Colette ENVIRONMENT AGENCY UK
Hagan, Madoc NUVIA LIMITED UK
Haigh, Paul THE PAUL HAIGH PARTNERSHIP UK
Hannon, Chris STUDSVIK UK UK
Hanson, Steven CH2M HILL UK
Hatt, Trevor ORTEC (AMETEK) UK
Hawe, Mike MAGNOX NORTH LTD UK
Hearn, Sue WEST CUMBRIA CONSULTING LTD UK
Hicks, Timothy GALSON SCIENCES LTD UK
141

142
Pre-Registered Attendees by Country
Holden, Gerry GRAVATOM UK
Hood, Malcolm SAFETY & ECOLOGY CORP LTD UK
Hudson, Phillip HEALTH & SAFETY EXECUTIVE UK
Hughes, Karl VT NUCLEAR SERVICES UK
Hunt, Jeremy SELLAFIELD LTD UK
Hunter, Tim UNIVERSITY OF LEEDS UK
Jacobs, Peter ATKINS LTD UK
Jain, Sneh LOUGHBOROUGH UNIVERSITY UK
Jarratt, Andrew SELLAFIELD LTD UK
John, Gordon AMEC UK
Jones, Philip MAGNOX NORTH UK
Kelly, Bernard UNIVERSITY OF MANCHESTER UK
Kerr, Robert SAFETY & ECOLOGY CORPORATION UK
Keyser, Ron ORTEC (AMETEK) UK
Kirschel, Miranda CH2M HILL UK
Koster, Dave AMEC UK
Kozlowska, Anna PROVECTUS GROUP LTD UK
Lee, David WASTE MANAGEMENT TECHNOLOGY UK
Lesinski, Mark MAGNOX SOUTH LTD UK
Lewcock, Andy ENERGY SOLUTIONS EU SERVICES LTD UK
Liddiard, Mark WORLEY PARSON UK
Lindberg, Maria STUDSVIK UK UK
Little, Richard QUINTESSA LIMITED UK
Lock, Bob NUVIA LIMITED UK
Lonergan, Patrick NRG UK
Lonsdale, John UNIVERSITY OF CENTRAL LANCASHIRE UK
Lord, Greg STOLLER UK UK
Loudon, David SELLAFIELD LTD UK
Loveland, Kaylin ENERGYSOLUTIONS ESEU LTD UK
Lowe, Andy UNIVERSITY OF MANCHESTER UK
Lowe, Tim UKAEA UK
Lyons, Mark L2 BUSINESS CONSULTING LIMITED UK
Macgregor, Alistair STUDSVIK UK UK
MacMillan, Amanda NIA UK
Major, Bob AMEC UK
Marsden, Gill NIS LTD UK
Marshall, Simon WESTINGHOUSE UK UK
McBarron, Martha AKER SOLUTIONS UK
McGill, Gerry AMEC UK
Medlock, Chris NUVIA LIMITED UK
Meehan, Adam MAGNOX SOUTH LTD UK
Mellor, Russ SELLAFIELD LTD UK
Mercer, John NUVIA LIMITED UK
Merrell, John WESTINGHOUSE ELECTRIC CO UK LTD UK
Metcalfe, Richard QUINTESSA LIMITED UK
Middlemas, Simon DOUNREAY SITE RESTORATION LTD UK
Milburn, Janet MAGNOX NORTH LTD UK
Milodowski, Tony BRITISH GEOLOGICAL SURVEY UK
Monks, Philip NIS LTD UK
Morris, Jenny GALSON SCIENCES LTD UK
Mort, Paul SELLAFIELD LTD UK
Mrowicki, Richard NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Munro, Andrew AMEC UK
North, Karan MAGNOX SOUTH LTD UK
Norwood, Keith BRITISH ENERGY UK
Ojovan, Michael UNIVERSITY OF SHEFFIELD UK
Orr, Peter ENVIRONMENT AGENCY UK
Page, Jim VENN ENGINEERING SERVICES LTD UK
Parker, Alan ENERGY SOLUTIONS UK
Parr, Corhyn NUCLEAR ENTERPRISE UK
Potter, Susan SELLAFIELD LTD UK
Pratley, Sonia AMEC UK
Raaz, Richard LLWR LTD UK
Rayner, Stephen VT NUCLEAR SERVICES UK
Reeves, Nigel AMEC UK
Roberts, John DALTON NUCLEAR INSTITUTE UK
Roberts, Peter TESSELLA UK
Robinson, Lynne SELLAFIELD LTD UK
Robson, Neil SELLAFIELD LTD UK
Robson, Phil WASTE MANAGEMENT TECHNOLOGY UK
Rogers, Graham NSG ENVIRONMENTAL LTD UK
Ross, Ann DSRL DOUNREAY UK
Rossiter, David LLW REPOSITORY LTD UK
Rule, Robert STRUCTURE VISION LIMITED UK
Sanders, Stephen OXFORD TECHNOLOGIES UK
Savage, David SELLAFIELD LTD UK
Scargill, Andy JORDAN NULCEAR UK
Selby, Terry URS CORPORATION UK
Shaw, Cath ENVIRONMENT AGENCY UK
Shaw, Richard BRITISH GEOLOGICAL SURVEY UK
Sheil, Fred SELLAFIELD LTD UK
Silvie, Jon BAE SYSTEMS UK
Simpson, Alan PAJARITO SCIENTIFIC CORP UK
Slaney, Brian COSTAIN OIL, GAS & PROCESS UK
Slater, Steven SELLAFIELD LTD UK
Snead, Kathryn US EPA UK
Steele, Carl SELLAFIELD LTD UK
Steele, Nicola SELLAFIELD LTD UK
Stewart, Alastair MAGNOX NORTH UK
Suckling, Paul QUINTESSA LIMITED UK
Tandy, Claire SELLAFIELD LTD UK
Thornton, Nigel ATKINS LTD UK
Todd, Roger NUVIA LIMITED UK
Toole, Joseph WORLEY PARSON UK
Towler, George QUINTESSA LIMITED UK
Travis, Mike ENERGYSOLUTIONS ESEU LTD UK
Turner, Tom RSRL UK
Waldeck, Peter NUVIA LIMITED UK
Warner, Ian MAGNOX NORTH UK
Waterman, Pippa ENERGYSOLUTIONS UK
Way, Robert SELLAFIELD LTD UK
West, Julia BRITISH GEOLOGICAL SURVEY UK
Wheeler, Ian SELLAFIELD LTD UK
White, Daniel URS WASHINGTON DIVISION UK
White, Matt GALSON SCIENCES LTD UK
Whitehead, Jim SELLAFIELD LTD UK
Whitton, John UK NATIONAL NUCLEAR LABORATORY UK
Wickham, Stephen GALSON SCIENCES LTD UK
Wilbraham, Richard LANCASTER UNIVERSITY UK
Wilcox, Steven AMEC UK
Wilks, Jeff URENCO UK LTD UK
Williams, Chris NUCLEAR INSTITUTE YGN UK
Williamson, Jack SELLAFIELD LTD UK
Wilson, Stuart SELLAFIELD LTD UK
Wilson Croft, Charles HILL INTERNATIONAL UK
Womack, Jonathan SCIENTIFICS LTD UK
Wyness, Alistair URS CORPORATION UK
Yetts, Robert SELLAFIELD LTD UK
Anderson, Keith D. ECC USA
Arno, Janine FOXFIRE SCIENTIFIC USA
Arno, Matthew FOXFIRE SCIENTIFIC USA
Benda, Gary USA
Bendo, John ASME USA
Bhattacharyya, Samit SAVANNAH RIVER NATIONAL USA
LABORATORY
Brown, Steven SENES CONSULTANTS LTD USA
Bushart, Sean ELECTRIC POWER RESEARCH INSTITUTE USA
Cull, Michael TELEDYNE BROWN ENGINEERING INC USA
Deiters, Michael PROJECT TIME & COST INC USA
Denton, Mark KURION INC USA
Desrosiers, Arthur SAFETY & ECOLOGY CORP USA
Devgun, Jas SARGENT & LUNDY USA
Duncan, Randall WESTINGHOUSE USA
Fallon, Mark CH2M HILL USA
Farrell, Shannon CH2M HILL USA
Gilbertson, Mark USA DOE USA
Gregory, Phil URS WASHINGTON TRU SOLUTIONS USA
Griffin, Jeff SRNL USA
Gubanc, Paul URS WASHINGTON DIVISION USA
Hall, Jim URS WASHINGTON DIVISION USA
Halter, Don FOXFIRE SCIENTIFIC USA
Hamilton, Ian FOXFIRE SCIENTIFIC USA
Han, Ana US DEPARTMENT OF ENERGY USA
Hickey, Cathy URS WD USA
Hickman, Paul PERMA-FIX ENVIRONMENTAL USA
SERVICES INC
Hobbs, David SAVANNAH RIVER NATIONAL USA

Pre-Registered Attendees by Country
LABORATORY
IdekerMulligan, Virgene AMERICAN RADIATION SERVICES INC USA
Jones, Angie AMEC USA
Kelbba, Heather NUCLEAR FILTER TECHNOLOGY USA
Kelley, Dennis PACIFIC NUCLEAR SOLUTIONS USA
Kok, Ken ASME USA
Lehew, John CH2M HILL PLATEAU USA
REMEDIATION COMPANY
Lively, Jeff MACTEC USA
Longsworth, Paul FLUOR CORPORATION USA
Lopez, Alex MACTEC INC USA
Maranville, Vickie AMEC EARTH & ENVIRONMENTAL USA
Marra, James SRNL USA
McCord, John S.M. STOLLER CORPORATION USA
Mintz, Morris PACTEC INC USA
Monts, David MISSISSIPPI STATE UNIVERSITY ICET USA
Morris, Ron WESTINGHOUSE USA
Negin, Chuck PROJECT ENHANCEMENT CORPORATION USA
Nigam, Hitesh DEPARTMENT OF ENERGY USA
Peake, Tom US EPA USA
Pickett, David CNWRA SOUTHWEST USA
RESEARCH INSTITUTE
Pre-Registered Attendees by Last Name
Adamson, David SELLAFIELD LTD UK
Adebanjo, Ayotunde SELLAFIELD LTD UK
Adina, Sandru SC MATE-FIN SRI Romania
Akhtar, Shuaib TESSELLA UK
Alderson, Ian NUCLEAR TECHNOLOGIES PLC UK
Alexander, Russell BEDROCK GEOSCIENCES Switzerland
Alexander, Ellie ATKINS UK
Amamoto, Ippei JAPAN ATOMIC ENERGY AGENCY Japan
Amos, Sean AWE PLC UK
Anderson, Keith D. ECC USA
Andersson, Johan JA STREAMFLOW AB Sweden
Anderton, Bill NUCLEAR MANAGEMENT PARTNERS UK
Andrieux, Fabrice LANCASTER UNIVERSITY UK
Anraku, Sohtaro HOKKAIDO UNIVERSITY Japan
Antrobus, Julianne NUVIA LIMITED UK
Antus, Andrea PAKS NUCLEAR POWER PLANT LTD Hungary
Arno, Janine FOXFIRE SCIENTIFIC USA
Arno, Matthew FOXFIRE SCIENTIFIC USA
Arnold, David HALLIN ROBOTICS LTD UK
Askew, Graeme SELLAFIELD LTD UK
Asou, Marielle COMMISSARIAT A L’ENERGIE ATOMIQUE France
Astrop, Amanda STUDSVIK UK UK
Atyeo, Paul RSRL UK
Aymanns, Katharina FORSCHUNGSZENTRUM JÜLICH GMBH Germany
Bacon, Michael HEALTH & SAFETY EXECUTIVE UK
Baines, Kim RSK RADIOLOGICAL UK
Bakari, Mohamed LANCASTER UNIVERSITY UK
Baker, Andrew ANDY BAKER CONSULTING UK
Baker, Jonathan CH2M HILL UK
Ball, John NUVIA LIMITED UK
Banford, Anthony NATIONAL NUCLEAR LABORATORY UK
Barre, Yves COMMISSARIAT À L’ENERGIE ATOMIQUE France
Bartlett, Angela UKAEA UK
Bath, Adrian INTELLISCI LTD UK
Beadle, Ian AMEC UK
Becker, Dirk-Alexander GRS MBH Germany
Benda, Gary USA
Bendo, John ASME USA
Bentley, Martin SELLAFIELD LTD UK
Berry, Robert FOXFIRE SCIENTIFIC INC UK
Berta, Zsolt MECSEK-ÖKO CO Hungary
Bhattacharyya, Samit SAVANNAH RIVER NATIONAL USA
LABORATORY
Biggs, Simon UNIVERSITY OF LEEDS UK
Blackmore, Jonathan RSRL UK
Bleasdale, Peter WASTE MANAGEMENT TECHNOLOGY UK
Blundell, Neil HEALTH & SAFETY EXECUTIVE UK
Boath, David AMEC UK
Plys, Martin FAUSKE & ASSOCIATES, LLC USA
Price, Mark PAR SYSTEMS INC USA
Reape, Andrew PROJECT TIME & COST INC USA
Rima, Steve MACTEC DEVELOPMENT CORPORATION USA
Rosnick, Reid US EPA USA
Schilling, Mike PACTEC INC USA
Scott, L. Max LOUISIANA STATE UNIVERSITY USA
Shrum, Daniel ENERGYSOLUTIONS USA
Subiry, Juan NAC INTERNATIONAL USA
Triay, Dr. Ines ASSISTANT SECRETARY- USA
US DOE EM PROGRAMS
Wallace, David CDM FEDERAL PROGRAMS USA
Waugh, Jody S. M. STOLLER CORPORATION USA
Wellman, Dawn US DEPARTMENT OF ENERGY USA
Wickland, Terry NUCLEAR FILTER TECHNOLOGY USA
Witwer, Keith IMPACT SERVICES INC USA
GEOMELT DIVISION
Forström, Hans DIRECTOR OF NUCLEAR FUEL CYCLE
AND WASTE TECHNOLOGY IAEA
Henwood, Stephen NUCLEAR DECOMMISSIONING
AUTHORITY
Bolton, Gary INDUSTRIAL TOMOGRAPHY SYSTEMS UK
Booth, Clare SELLAFIELD LTD UK
Booth, Peter NNL LTD UK
Borchardt, Ralf ENERGIEWESHE NOID GMBH Germany
Boxall, Colin LANCASTER UNIVERSITY UK
Broadbent, Craig STUDSVIK UK UK
Bromley, Michael LANCASTER UNIVERSITY UK
Brookes, Christopher SELLAFIELD LTD UK
Brooks, Sheila ATOMIC ENERGY OF CANADA Canada
Brown, Steven SENES CONSULTANTS LTD USA
Browning, Stephen NUCLEAR TECHNOLOGIES PLC UK
Bruce, Georgina SELLAFIELD LTD UK
Bull, Richard NUVIA LIMITED UK
Burgess, Pete NUVIA LIMITED UK
Burke, Stephen NUCLEAR TECHNOLOGIES PLC UK
Burns, Kevin SELLAFIELD LTD UK
Bushart, Sean ELECTRIC POWER RESEARCH INSTITUTE USA
Butez, Marc CEA France
Butter, Kevin WASTE MANAGEMENT TECHNOLOGY UK
Cabrera, David MAGNOX NORTH UK
Cadini, Francesco POLITECNICO DI MILANO Italy
Campbell, Colin SELLAFIELD LTD UK
Campbell, Graham NUCLEAR MANAGEMENT PARTNERS UK
Candy, Simon SELLAFIELD LTD UK
Cane, Vince NUCLEAR TECHNOLOGIES PLC UK
Carlsson, Jan SKB Sweden
Carrick, Jim URS WASHINGTON DIVISION UK
Case, Keith SELLAFIELD LTD UK
Cassidy, Helen SELLAFIELD LTD UK
Cassidy, James FATHOMS UK
Caunt, John JCS UK
Cha, Jeonghun KAERI S. Korea
Chadwick, Dominic UNIVERSITY OF MANCHESTER UK
Cheek, John SIEMPELKAMP NUCLEAR TECHNOLOGY UK
Chiba, Tamotsu JGC CORPORATION UK
Chorley, Gary SELLAFIELD LTD UK
Christie, Dylan NRG UK
Clark, Anna NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Clark, Matthew NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Clark, Peter VT NUCLEAR SERVICES UK
Cochrane, Jim SEPA UK
Codée, Hans COVRA Netherlands
Connolly, Mike IDAHO NATIONAL LABORATORY UK
Conroy, Julie MAGNOX NORTH UK
Cook, Laurence SELLAFIELD LTD UK
Cooper, John NUCLEAR ENGINEERING SERVICES LTD UK
Coppins, Gavin UKAEA UK
143

144
Pre-Registered Attendees by Last Name
Craze, Andrew NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Crossland, Ian CROSSLAND CONSULTING UK
CsQvári, Mihaly MECSEK-ÖKO CO Hungary
Cuchet, Jean-Marie BELGONUCLEAIRE Belgium
Cull, Michael TELEDYNE BROWN ENGINEERING INC USA
Cunningham, Bernard BIRSE NUCLEAR UK
Currie, Ian AMEC UK
Curry, Daniel URS CORPORATION UK
Darroch, Norman BABCOCK MARINE UK
Davey, Richard SELLAFIELD LTD UK
Davies, Phil NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Davies, Tim UKAEA UK
De la Gardie, Fredrik SKB UK
De Sanctis, Jacopo POLITECNICO DI MILANO UK
De Vos, Renate NRG Netherlands
Dean, Julian NATIONAL PHYSICAL LABORATORY UK
Deehan, Connor ATKINS LTD UK
Deeran, Paul FRASHER-NASH CONSULTANTS UK
Deiters, Michael PROJECT TIME & COST INC USA
Delaney, Brian HEALTH & SAFETY EXECUTIVE UK
Denton, Mark KURION INC USA
Desrosiers, Arthur SAFETY & ECOLOGY CORP USA
Devgun, Jas SARGENT & LUNDY USA
Dodd, Kevin STUDSVIK UK UK
Drace, Zoran IAEA Austria
Drulia, Mark ENERGYSOLUTIONS UK
Duncan, Paul SCIENTIFICS LTD UK
Duncan, Randall WESTINGHOUSE USA
Duro, Lara AMPHOS 21 Spain
Dux, Joachim WAK GMBH UK
D’vaz, Mark SELLAFIELD LTD UK
Edmiston, Lindsay NATIONAL NUCLEAR LABORATORY UK
Ehamparadasan, Raveenth PARSONS BRINCKERHOFF UK
Ehrlicher, Ulrich PSA Switzerland
Eichhorn, Heiko NUKEM TECHNOLOGIES GMBH Germany
Elter, EnikQ PAKS NUCLEAR POWER PLANT LTD Hungary
Emptage, Matthew ENVIRONMENT AGENCY UK
Eng, Torsten SKB Sweden
Fabjan, Marija AGENCY FOR RADWASTE MANAGEMENT Slovenia
Fachinger, Johannes FURNACES NUCLEAR APPLICATIONS Germany
Fairweather, Michael UNIVERSITY OF LEEDS UK
Fallon, Mark CH2M HILL USA
Fares, Toby ATOMIS ENERGY COMMISSION (CEA) France
Farrell, Shannon CH2M HILL USA
Ferrus, Joel URS FRANCE France
Fitzpatrick, Jonathan ATOMIC ENERGY OF CANADA Canada
Földing, Gabor MECSEK-ÖKO CO Hungary
Forström, Hans DIRECTOR OF NUCLEAR FUEL CYCLE
AND WASTE TECHNOLOGY IAEA
Fowler, Julian TESSELLA UK
Fransen, Ivo BELOGOPROCESS N.V Belgium
Fretwell, Rod JORDAN NULCEAR UK
Fritz, Laszlo PUBLIC LIMITED COMPANY FOR Hungary
RADIOACTIVE WASTE MAN.
Gaus, Irina NAGRA Switzerland
Gechikov, Mark AMEC NSS Canada
Geiser, Heinz GNS GESELLSCHAFT F NUCLEAR Germany
SERVICE MBH
George, David URS UK
Gibson, Keith LLW REPOSITORY UK
Gifford-Nash, Tim MAGNOX SOUTH LTD UK
Gilbertson, Mark USA DOE USA
Giroir, Bob MAGNOX NORTH LTD UK
Gleason, Gene NAC INTERNATIONAL UK
Glorennec, Christian EDF France
Glover, Alec SELLAFIELD LTD UK
Goldsworthy, Martin GOLDER ASSOCIATES Peru
Goyal, Kapil LOS ALAMOS NATIONAL LABS Albania
Graf, Reinhold GNS MBH Germany
Gregory, Phil URS Washington TRU Solutions USA
Griffin, Jeff SRNL USA
Gruendler, Detlef ISTEC Germany
Grundy, Colette ENVIRONMENT AGENCY UK
Gubanc, Paul URS WASHINGTON DIVISION USA
Hafen, Hubert WÄLISCHMILLER ENGINEERING GMBH Germany
Hagan, Madoc NUVIA LIMITED UK
Haigh, Paul THE PAUL HAIGH PARTNERSHIP UK
Hall, Jim URS WASHINGTON DIVISION USA
Halter, Don FOXFIRE SCIENTIFIC USA
Hamilton, Ian FOXFIRE SCIENTIFIC USA
Han, Ana US DEPARTMENT OF ENERGY USA
Hannon, Chris STUDSVIK UK UK
Hanson, Steven CH2M HILL UK
Harjula, Risto HELSINKI UNIVERSITY Finland
Hatt, Trevor ORTEC (AMETEK) UK
Haverkamp, Bernt DBE TECHNOLOGY GMBH Germany
Havlova, Vaclava NUCLEAR RESEARCH INST. REZ PLC Czech
Republic
Hawe, Mike MAGNOX NORTH LTD UK
Hearn, Sue WEST CUMBRIA CONSULTING LTD UK
Henwood, Stephen NUCLEAR DECOMMISSIONING AUTHORITY,
Hertl, Bojan AGENCY FOR RADWASTE MANAGEMENT Slovenia
Hickey, Cathy URS WD USA
Hickman, Paul PERMA-FIX ENVIRONMENTAL USA
SERVICES INC
Hicks, Timothy GALSON SCIENCES LTD UK
Hillebrand, Guenter NUCLEAR ENGINEERING Austria
Hobbs, David SAVANNAH RIVER NATIONAL USA
LABORATORY
Holden, Gerry GRAVATOM UK
Hood, Malcolm SAFETY & ECOLOGY CORP LTD UK
Hornung, Frederic COMMISSARIAT A L’ENERGIE ATOMIQUE France
Hudson, Phillip HEALTH & SAFETY EXECUTIVE UK
Hughes, Lisa NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Hughes, Karl VT NUCLEAR SERVICES UK
Hunt, Stuart NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Hunt, Jeremy SELLAFIELD LTD UK
Hunter, Tim UNIVERSITY OF LEEDS UK
Husain, Aamir KINECTRICS INC Canada
IdekerMulligan, Virgene AMERICAN RADIATION SERVICES INC USA
Iguchi, Yukihiro JAPAN NUCLEAR ENERGY SAFETY Japan
ORGANISATION
Ishii, Nobuyoshi NATIONAL INSTITUTE OF Japan
RADIOLOGICAL SCIENCES
Ishikura, Takeshi THE INSTITUTE OF APPLIED ENERGY Japan
Jacobs, Peter ATKINS LTD UK
Jain, Sneh LOUGHBOROUGH UNIVERSITY UK
Jakusz, Susann HANSA PROJEKT ANLAGENTECHNIK Germany
GMBH
Jarratt, Andrew SELLAFIELD LTD UK
Jeanjacques, Michel COMMISSARIAT À L’ENERGIE ATOMIQUE France
John, Gordon AMEC UK
Jones, Philip MAGNOX NORTH UK
Jones, Angie AMEC USA
Källström, Klas SVENSK KÄRNBRÄNSLEHANTERING AB Sweden
Kapitany, Sandor PUBLIC LIMITED COMPANY Hungary
FOR RADIOACTIVE WASTE MAN.
Kelbba, Heather NUCLEAR FILTER TECHNOLOGY USA
Kelley, Dennis PACIFIC NUCLEAR SOLUTIONS USA
Kelly, Bernard UNIVERSITY OF MANCHESTER UK
Kerr, Robert SAFETY & ECOLOGY CORPORATION UK
Kerwin, Richard GLOBAL PARTNERSHIP Canada
PROGRAMME (IGX)
Keyser, Ron ORTEC (AMETEK) UK
Kienzler, Bernhard FORSCHUNGSZENTRUM KARLSRUHE Germany
Kirschel, Miranda CH2M HILL UK
Kitamura, Koichi JAPAN ATOMIC ENERGY AGENCY Japan
Kok, Ken ASME USA
Koster, Dave AMEC UK
Kozlowska, Anna PROVECTUS GROUP LTD UK
Kozyrev, Denis RADIOACTIVE WASTE Russia
MANAGEMENT ENTERPRISE
Kralj, Metka AGENCY FOR RADWASTE MANAGEMENT Slovenia
Krasznai, John KINECTRICS INC Canada
Krone, Jürgen DBE TECHNOLOGY GMBH Germany
Kugel, Karin FEDERAL OFFICE FOR RADIATION Germany
PROTECTION

Pre-Registered Attendees by Last Name
Kulikov, Konstantin NIPTB ONEGA Russia
Lai, Hung-Chih FCMA Taiwan
Lara, Esperanza CIEMAT Spain
Laraia, Michele IAEA Austria
Lee, David WASTE MANAGEMENT TECHNOLOGY UK
Lehew, John CH2M HILL PLATEAU REMEDIATION USA
COMPANY
Lesinski, Mark MAGNOX SOUTH LTD UK
Lewcock, Andy ENERGY SOLUTIONS EU SERVICES LTD UK
Liddiard, Mark WORLEY PARSON UK
Lindberg, Maria STUDSVIK UK UK
Lindskog, Staffan SSM Sweden
Little, Richard QUINTESSA LIMITED UK
Lively, Jeff MACTEC USA
Lock, Bob NUVIA LIMITED UK
Lonergan, Patrick NRG UK
Longsworth, Paul FLUOR CORPORATION USA
Lonsdale, John UNIVERSITY OF CENTRAL LANCASHIRE UK
Lopez, Alex MACTEC INC USA
Lord, Greg STOLLER UK UK
Loudon, David SELLAFIELD LTD UK
Loveland, Kaylin ENERGYSOLUTIONS ESEU LTD UK
Lowe, Andy UNIVERSITY OF MANCHESTER UK
Lowe, Tim UKAEA UK
Luycx, Paul CASTER CONSULTING Belgium
Lyons, Mark L2 BUSINESS CONSULTING LIMITED UK
Macgregor, Alistair STUDSVIK UK UK
MacMillan, Amanda NIA UK
Major, Bob AMEC UK
Makino, Hitoshi JAPAN ATOMIC ENERGY AGENCY Japan
Maltsev, Alexey JSC Russia
Maranville, Vickie AMEC EARTH & ENVIRONMENTAL USA
Marra, James SRNL USA
Marsden, Gill NIS LTD UK
Marshall, Simon WESTINGHOUSE UK UK
Martensson, Per SWEDISH NUCLEAR FUEL & Sweden
WASTE MANAGEMENT CO
McBarron, Martha AKER SOLUTIONS UK
McCombie, Charles ARIUS ASSOCIATION Switzerland
McCord, John S.M. STOLLER CORPORATION USA
McGill, Gerry AMEC UK
McKinley, Ian MCKINLEY CONSULTING Switzerland
McKinney, James NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
McMinn, Mervin NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Medlock, Chris NUVIA LIMITED UK
Meehan, Adam MAGNOX SOUTH LTD UK
Mellor, Russ SELLAFIELD LTD UK
Mercer, John NUVIA LIMITED UK
Merrell, John WESTINGHOUSE ELECTRIC CO UK LTD UK
Metcalfe, Doug NATURAL RESOURCES CANADA Canada
Metcalfe, Richard QUINTESSA LIMITED UK
Middlemas, Simon DOUNREAY SITE RESTORATION LTD UK
Milburn, Janet MAGNOX NORTH LTD UK
Millan, Miguel WESTINGHOUSE Spain
Miller, Charles U.S. NUCLEAR REGULATORY Andorra
COMMISSION
Milodowski, Tony BRITISH GEOLOGICAL SURVEY UK
Mimura, Hitoshi TOHOKU UNIVERSITY Japan
Mingrone, Giorgio SOGIN SPA Italy
Mintz, Morris PACTEC INC USA
Misra, Shri BHABHA ATOMIC RESEARCH CENTRE India
Monks, Philip NIS LTD UK
Monts, David MISSISSIPPI STATE UNIVERSITY ICET USA
Morris, Jenny GALSON SCIENCES LTD UK
Morris, Ron WESTINGHOUSE USA
Mort, Paul SELLAFIELD LTD UK
Mrowicki, Richard NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Mukunoki, Atsushi JGC CORPORATION Japan
Muldoon, Joe SASKATCHEWAN RESEARCH COUNCIL Canada
Munro, Andrew AMEC UK
Negin, Chuck PROJECT ENHANCEMENT CORPORATION USA
Nigam, Hitesh DEPARTMENT OF ENERGY USA
Nishimoto, Shoji NAGOYA CITY SCIENCE MUSEUM Japan
North, Karan MAGNOX SOUTH LTD UK
Norwood, Keith BRITISH ENERGY UK
Noseck, Ulrich GRS MBH Germany
Ohno, Shintaro KAJIMA CORPORATION Japan
Ojovan, Michael UNIVERSITY OF SHEFFIELD UK
Ooms, Bart BELGOPROCESS Belgium
Orr, Peter ENVIRONMENT AGENCY UK
Osawa, Hideaki JAPAN ATOMIC ENERGY AGENCY Japan
Paajanen, Airi UNIVERSITY OF HELSINKI Finland
Page, Jim VENN ENGINEERING SERVICES LTD UK
Palmu, Marjatta POSIVA OY Finland
Panik, Michal SLOVAK UNIVERSITY OF TECHNOLOGY Slovakia
Parker, Alan ENERGY SOLUTIONS UK
Parr, Corhyn NUCLEAR ENTERPRISE UK
Peake, Tom US EPA USA
Perko, Janez SCK CEN Belgium
Pickett, David CNWRA SOUTHWEST USA
RESEARCH INSTITUTE
Plys, Martin FAUSKE & ASSOCIATES, LLC USA
Popov, Dmitry RADIOACTIVE WASTE MANAGEMENT Russia
ENTERPRISE
Poskas, Povilas LITHUANIAN ENERGY INSTITUE Lithuania
Posnatzki, Britta TUEV NORD ENSYS HANOVER Germany
GMBH & CO KG
Potter, Susan SELLAFIELD LTD UK
Pratley, Sonia AMEC UK
Price, Mark PAR SYSTEMS INC USA
Raaz, Richard LLWR LTD UK
Radohhe, Tanguy TRACTEBEL ENGINEERING Belgium
Rayner, Stephen VT NUCLEAR SERVICES UK
Reape, Andrew PROJECT TIME & COST INC USA
Reeves, Nigel AMEC UK
Reich, Claudia WÄLISCHMILLER ENGINEERING GMBH Germany
Rendell, Philip NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Richter, Anke FZ DRESDEN ROSSENDORF Germany
Rieger, Ulrich FEDERAL MINISTRY OF ECONOMICS Germany
& TECHNOLOGY
Rima, Steve MACTEC DEVELOPMENT CORPORATION USA
Roberts, John DALTON NUCLEAR INSTITUTE UK
Roberts, Peter TESSELLA UK
Robinson, Lynne SELLAFIELD LTD UK
Robson, Neil SELLAFIELD LTD UK
Robson, Phil WASTE MANAGEMENT TECHNOLOGY UK
Rogers, Graham NSG ENVIRONMENTAL LTD UK
Rosnick, Reid US EPA USA
Ross, Ann DSRL DOUNREAY UK
Rossiter, David LLW REPOSITORY LTD UK
Roth, Andreas HANSA PROJEKT ANLA Germany
GENTECHNIK GMBH
Rule, Robert STRUCTURE VISION LIMITED UK
Sanders, Stephen OXFORD TECHNOLOGIES UK
Sasaki, Michiya CRIEPI Japan
Savage, David SELLAFIELD LTD UK
Scargill, Andy JORDAN NULCEAR UK
Scheffler, Beate NUKEM TECHNOLOGIES GMBH Germany
Schilling, Mike PACTEC INC USA
Schneider, Jürg NAGRA Switzerland
Schramm, Laurier SASKATCHEWAN RESEARCH COUNCIL Canada
Schumann, Dorothea PAUL SCHERRER INSTITUTE Switzerland
Schwall, Sebastian FORSCHUNGSZENTRUM JÜLICH GMBH Germany
Scott, L. Max LOUISIANA STATE UNIVERSITY USA
Sedor, Kelly NUCLEAR WASTE MANAGEMENT Canada
ORGANIZATION
Selby, Terry URS CORPORATION UK
Semba, Takeshi JAPAN ATOMIC ENERGY AGENCY Japan
Shaw, Cath ENVIRONMENT AGENCY UK
Shaw, Richard BRITISH GEOLOGICAL SURVEY UK
Sheil, Fred SELLAFIELD LTD UK
Shimada, Taro JAPAN ATOMIC ENERGY AGENCY Japan
Shrum, Daniel ENERGYSOLUTIONS USA
Silvie, Jon BAE SYSTEMS UK
Sim, Eunice DSO NATIONAL LABORATORIES Singapore
Simenon, Ronny NIRAS/ONDRAF Belgium
145

146
Pre-Registered Attendees by Last Name
Simpson, Alan PAJARITO SCIENTIFIC CORP UK
Siripornadulsil, Wilailak Khon Kean University Thiland
Siripornadulsil, Surasak Khon Kean University Thiland
Sjöblom, Rolf TEKEDO AB Sweden
Slaney, Brian COSTAIN OIL, GAS & PROCESS UK
Slater, Steven SELLAFIELD LTD UK
Snead, Kathryn US EPA UK
Sokcic-Kostic, Marina NUKEM TECHNOLOGIES GMBH Germany
Song, Myung-Jae DOOSAN HEAVY INDUSTRIES & S. Korea
CONSTRUCTION
Steele, Carl SELLAFIELD LTD UK
Steele, Nicola SELLAFIELD LTD UK
Steinkuhler, Claude DDR CONSULT Belgium
Stenmark, Anders STUDSVIK NUCLEAR AB Sweden
Stepanik, Terry ATOMIC ENERGY OF CANADA Canada
Stewart, Alastair MAGNOX NORTH UK
Stockmann, Madlen FZ DRESDEN ROSSENDORF Germany
Strelzig, Maja TUEV NORD ENSYS HANOVER Germany
GMBH & CO KG
Subiry, Juan NAC INTERNATIONAL USA
Suckling, Paul QUINTESSA LIMITED UK
Sykes, Jon UNIVERSITY OF WATERLOO Canada
Takats, Ferenc GOLDER ASSOCIATES HUNGARY Hungary
Tandy, Claire SELLAFIELD LTD UK
Teodorov, Gabriela SC MATE_FIN SRI Romania
Thornton, Nigel ATKINS LTD UK
Todd, Roger NUVIA LIMITED UK
Toole, Joseph WORLEY PARSON UK
Toro, Laszlo SC MATE_FIN SRI Romania
Torstenfelt, Börje SWEDISH NUCLEAR FUEL & Sweden
WASTE MANAGEMENT CO
Touhey, Malcolm INTERNATIONAL NUCLEAR SERVICES UK
Towler, George QUINTESSA LIMITED UK
Travis, Mike ENERGYSOLUTIONS ESEU LTD UK
Triay, Dr. Ines ASSISTANT SECRETARY- USA
US DOE EM PROGRAMS
Turner, Roland SWEDISH RADIATION SAFETY Sweden
AUTHORITY
Turner, Tom RSRL UK
Tusa, Esko FORTUM NUCLEAR SERVICES Ltd Finland
Umeki, Hiroyuki JAEA Japan
Van Velzen, Leo NUCLEAR RESEARCH & Netherlands
CONSULTANCY GROUP
Vanderperre, Serge TRACTEBEL ENGINEERING Belgium
Verhoef, Ewoud COVRA N.V Netherlands
Vesely, Andreas NUCLEAR ENGINEERING SEIBERSDORF Austria
Viermann, Jörg GNS GESELLSCHAFT F NUCLEAR Germany
SERVICE MBH
Virsek, Sandi ARAO Slovania
Vomvoris, Efstratios NAGRA Switzerland
Vuillier, Stephane SGN AREVAS GROUP France
Waldeck, Peter NUVIA LIMITED UK
Wallace, David CDM FEDERAL PROGRAMS USA
Wareing, Mark NUCLEAR DECOMMISSIONING UK
AUTHORITY NDA
Warner, Ian MAGNOX NORTH UK
Washer, Michael FOREIGN AFFAIRS & Canada
INTERNATIONAL TRADE CANADA
Waterman, Pippa ENERGYSOLUTIONS UK
Waugh, Jody S. M. STOLLER CORPORATION USA
Way, Robert SELLAFIELD LTD UK
Weil, Leopold FEDERAL OFFICE FOR RADIATION Germany
PROTECTION
Welbergen, Jeroen COVRA Netherlands
Wellman, Dawn US DEPARTMENT OF ENERGY USA
West, Julia BRITISH GEOLOGICAL SURVEY UK
Wheeler, Ian SELLAFIELD LTD UK
White, Daniel URS WASHINGTON DIVISION UK
White, Matt GALSON SCIENCES LTD UK
Whitehead, Jim SELLAFIELD LTD UK
Whitton, John UK NATIONAL NUCLEAR LABORATORY UK
Wickham, Stephen GALSON SCIENCES LTD UK
Wickland, Terry NUCLEAR FILTER TECHNOLOGY USA
Wilbraham, Richard LANCASTER UNIVERSITY UK
Wilcox, Steven AMEC UK
Wilks, Jeff URENCO UK LTD UK
Williams, Chris NUCLEAR INSTITUTE YGN UK
Williamson, Jack SELLAFIELD LTD UK
Wilson, Stuart SELLAFIELD LTD UK
Wilson Croft, Charles HILL INTERNATIONAL UK
Witwer, Keith IMPACT SERVICES INC USA
GEOMELT DIVISION
Woerner, Jörg RD HANAU Germany
Womack, Jonathan SCIENTIFICS LTD UK
Wyness, Alistair URS CORPORATION UK
Yetts, Robert SELLAFIELD LTD UK
Yoshida, Hidekazu NAGOYA UNIVERSITY Japan
Zachar, Matej SLOVAK UNIVERSITY OF TECHNOLOGY Slovakia
Zielonka, Holger TUEV NORD ENSYS HANOVER Germany
GMBH & CO KG
Zorzoli, Franco CAMPOVERDE SRL Italy

ICEM’09 <strong>Conference</strong> Program Organizers
Steering Committee
<strong>Conference</strong> General Co-Chairs
Kenneth Kok, URS Washington Division
Fred Sheil, Sellafield Ltd.
<strong>Conference</strong> Manager
Gary Benda
ICEM Project Director(s)
John Bendo, ASME
Maureen Carter, Institution of Mechanical Engineers
Technical Program Co-Chair(s)
Jennifer Biedscheid, Washington TRU Solutions
David Boath, AMEC Nuclear
Terry Wickland, Nuclear Filter Technology
Technical Paper Submission; Abstracts, Bio’s, Copyright,
drafts and/or Final Papers
Stacey Cooper, ASME
John Bendo, ASME
Shari Brabham, CISS Corporation
US Program Coordinator for all Technical Program Chairs and
all Non-EU Registrations and Exhibition/Sponsorship Sales
Shari Brabham - CISS Corporation
EU <strong>Conference</strong> Facilities, Social Programs, Golf, Local Aspects
Amelia Brunt - Institution of Mechanical Engineers
EU and Non-EU Exhibition Coordination
Aman Duggal - Institution of Mechanical Engineers
EU Registration Coordination
Tina Churcher, Institution of Mechanical Engineers
Guest Tours
Dianne Benda, Tour Liaison & Coordinator
Technical Tours
Ian Currie, Nuclear Institute
US Federal Liaison(s)
Kurt Gerdes, US Department of Energy
Ana Han, US Department of Energy
UK Government Liaison
Richard Mrowicki, Nuclear Decommissioning Authority
ASME ICEM’09 <strong>Conference</strong> Committee Liaisons
John Bendo, (ASME)
ASME Nuclear Engineering Division (NED)
Kenneth Kok, (WSMS)
ASME Environmental Engineering Division (EED)
Gary Benda, (ICEM’09 <strong>Conference</strong> Manager)
Institution of Mechanical Engineers
Maureen Carter, Institution of Mechanical Engineers
Nuclear Institute (NI)
Fred Sheil, Sellafield Ltd.
Technical Program - Track Co-Chairs
Low/Intermediate-Level Waste Management
Angie Jones, AMEC Earth & Environmental (USA)
Alun Ellis, Radioactive WM Directorate (UK)
Spent Fuel, Fissile, Trancuranic, High Level Waste Management
Murthy Devarakonda, Washington Group <strong>International</strong> (USA)
Mark Gilbertson, EM-USDOE (USA)
Gerry McGill, Nuclear Management Partners (UK)
Facility Decontamination and Decommissioning
Jas Devgun, Sargent & Lundy, LLC (USA)
Michael Laria, IAEA (AUSTRIA)
Environmental Remediation
Steve Brown, SENES Consultants, Ltd (USA)
Leo van Velzen, Nuclear Research & Consultancy Group
(SWITZERLAND)
Environmental Management / Public Involvement
Jennifer Biedscheid, Washington TRU Solutions (USA)
Emmy Roos, Belgoprocess (BELGIUM)
Session Organizers
Russell Alexander, Bedrock Geosciences, SWITZERLAND
Ed Alperin, <strong>The</strong> Shaw Group, US
Keith Anderson, ECC, US
Axel Baecker, EWN, UK
Anthony Banford, NNL, UK
Ian Beadle, AMEC, UK
Gary Benda, ICEM’09 <strong>Conference</strong> Manager, US
John Bendo, ASME, US
Ed Bentz, E.J. Bentz & Associates, US
Peter Berneckee, BFS, GERMANY
Robert Berry, Foxfire Scientific, Inc., UK
Jennifer Biedscheid, Washington Division of URS, USA
Steve Brown, SENES Consultants Ltd., US
Sean Bushart, EPRI, US
Simon Candy, Sellafield Ltd., UK
Han Codee, COVRA N.V., NETHERLANDS
Ian Crossland, Crossland Consulting, UK
Jean-Marie Cuchet, Belgonucleaire, BELGIUM
Michael Cull, Teledyne Brown Engineering, Inc., US
Mark Denton, Kurion Inc., US
Murthy Devarakonda, Washington TRU Solutions, LLC., US
Jas Devgun, Sargent & Lundy, US
Zoran Drace, IAEA, AUSTRIA
Alun Ellis, NDA, UK
Mark Gerchikov, AMEC NSS, CANADA
Kapil Goyal, Los Alamos National Laboratory, US
Kurt Gerdes, US DOE, US
Jeff Griffin, Savannah Rover National Laboratory, US
Ana Han, US DOE, US
Cathy Hickey, URS, Washington Division, US
Natraj Iyer, Savannah River National Laboratory (USA)
Angie Jones, AMEC Earth & Environmental, US
Alex Jakubick, UMREG, AUSTRIA
Ron Keyser, ORTEC - AMETEK, US
Kenneth Kok, URS Washington Division, US
Grant Koroll, AECL, CANADA
Michael Laraia, IAEA, AUSTRIA
Christophe Le Goaller, CEA, FRANCE
Maria Lindberg, Studsvik Ltd., UK
Mark Lesinski, Magnox South Ltd., UK
Charles McCombie, Arius Associations, UK
Gerry McGill, AMEC, UK
Tony Milodowski, British Geological Survey, UK
Richard Mrowicki, NDA, UK
Virgene Mulligan, ARS <strong>International</strong>, US
Corhyn Parr, Nuclear Enterprise Ltd., UK
Neil Robson, Sellafield Ltd., UK
Michiya Sasaki, CRIEPE, JAPAN
Detlef Schmidt, Consultant, UK
Fred Sheil, Sellafield, Ltd, UK
Carl Steele, Sellafield, LTD., UK
Hiroyuki Umeki, JAEA, JAPAN
Pierre Van Iseghem, SCK•CEN, BELGIUM
Leo van Velzen, NRG, NETHERLANDS
Ian Wheeler, Sellafield Ltd., UK
Leopold Weil, BFS, GERMANY
David Wallace, CDM, US
Stephen Wickham, Galson Sciences, UK
Chris Williams, VT Nuclear Services, UK
147

148
Schedule of Events
Event Time Location
— SUNDAY, OCTOBER 11, 2009 - TENTATIVE —
Exhibitor Set up Hours pre-assigned ACC - Exhibition Hall 2A
Registration 16:00 - 19:00 ACC - 2nd Floor
Author/Panelist/Co-Chair Check-in 16:00 - 19:00 ACC - 2nd Floor
Welcome Reception 18:00 - 19:30 ACC - Exhibition Hall 2A
— MONDAY, OCTOBER 12, 2009 - TENTATIVE —
Registration 07:15 - 18:00 ACC - 2nd Floor
Speakers Ready Area 07:15 - 17:00 ACC - 2nd Floor, Room 7
Speakers Briefing/Breakfast 08:00 - 08.30 ACC - 2nd Floor, Room 11B
Coffee Service - Pre Opening Session 07:30 - 09:00 ACC - Exhibition Hall 2A
Author/Panelist/Co-Chair Check-in 07:15 - 18:00 ACC - 2nd Floor
Exhibition Open 07:30 - 18:00 ACC - Exhibition Hall 2A
Guest Welcome Reception/Tours 08:30 - 09:30 ACC - 2nd Floor, Room 14
Monday Morning Opening Session 09:00 - 12:30 ACC - 2nd Floor - Room 1
Coffee Break 10:30 - 11:00 ACC - Exhibition Hall 2A
Lunch 12:30 - 13:40 ACC - Exhibition Hall 2A
Poster Session 13:30 - 17:45 ACC - 2nd floor
Sessions 13:45 - 18:00 ACC - 2nd floor
Coffee Break 15:30 - 16:10 ACC - Exhibition Hall 2A
YGN General Meeting After Session 11A ACC - Room 13
— TUESDAY, OCTOBER 13, 2009 - TENTATIVE —
Registration 07:15 - 18:00 ACC - 2nd Floor
Speakers Briefing/Breakfast 07:30 - 08.00 ACC - 2nd Floor , Room 11B
Speakers Ready Area 07:15 - 17:00 ACC - 2nd Floor, Room 7
Author/Panelist/Co-Chair Check-in 07:15 - 18:00 ACC - 2nd Floor
Exhibit Hall Hours 07:30 - 19:30 ACC - Exhibition Hall 2A
Sessions 08:30 - 12:30 ACC - 2nd Floor
Poster Session 08:30 - 12:45 ACC - 2nd Floor
Coffee Break 10:15 - 10:40 ACC - Exhibition Hall 2A
Lunch 12:30 - 13:40 ACC - Exhibition Hall 2A
Sessions 13:45 - 18:00 ACC - 2nd Floor
Poster Session 13:30 - 17:45 ACC - 2nd Floor
Coffee Break 15:30 - 16:10 ACC - Exhibition Hall 2A
Tuesday Exhibit Reception 18:00 - 19:30 ACC - Exhibition Hall 2A
— WEDNESDAY, OCTOBER 14, 2009 - TENTATIVE —
Registration 07:15 - 18:00 ACC - 2nd Floor
Speakers Briefing/Breakfast 07:30 - 08.00 ACC - 2nd Floor, Room 11B
Speakers Ready Area 07:15 - 17:00 ACC - 2nd Floor, Room 7
Author/Panelist/Co-Chair Check-in 07:15 - 18:00 ACC - 2nd Floor
Exhibit Hall Hours 07:30 - 16:30 ACC - Exhibition Hall 2A
Sessions 08:30 - 12:30 ACC - 2nd Floor
Poster Session 08:30 - 12:45 ACC - 2nd Floor
ICEM’09 Lessons Learned 08:30 - 10:15 ACC - Room 14
ICEM’10 Plannng Meeting 10:40 - 12:30 ACC - Room 14
Coffee Break 10:15 - 10:40 Exhibition Hall 2A
Lunch 12:30 - 13:40 Exhibition Hall 2A
Sessions 13:45 - 18:00 ACC - 2nd Floor
Poster Session 13:30 - 17:45 ACC - 2nd Floor
Coffee Break 15:30 - 16:10 ACC - Exhibition Hall 2A
Last Bus Depart for the Adelphi Hotel 18:45 ACC - Mersey River Side
Wednesday Banquet Drinks/Reception 19:00 - 20:00 Britannia Adelphi Hotel
Wednesday Banquet Dinner/Band 20:00 - 23:45 Britannia Adelphi Hotel
Last Bus Returns to ACC 23:45 Britannia Adelphi Hotel
— THURSDAY, OCTOBER 15, 2009 - TENTATIVE —
Registration 07:15 - 10:00 ACC - 2nd floor
Speakers Ready Area Not Available ACC - Area not provided
Speakers Briefing/Breakfast 07:30 - 08.00 ACC - 2nd Floor, Room 11B
Author/Panelist/Co-Chair Check-in 07:15 - 12:30 ACC - 2nd Floor
Sessions 08:30 - 12:30 ACC - 2nd Floor
Coffee Break 10:15 - 10:40 ACC - 2nd Floor
<strong>Conference</strong> Ends 12:30 We thank you for attending.
Technical Tours Departure Various Times on Thursday Departs ACC - Mersey River Side
Guest Tours Departure Various Times Departs ACC - Mersey River Side

Convention Center — Cross Section of All Three Levels
Escalator to
the 1st floor
1. Convention Center Entrance
1st Floor
4. Exhibition Hall Entrance
Basement Level
Convention Center — 2nd Floor
Entrance at 1st Floor
2. Registration and Technical Meeting Ro oms 3. Loading Bay
(Riverside Terrace) — 2nd Floor
Basement Level
5. River Mersey 6. Bus Loading Area
Entrance at 1st Floor
Registration Area
Meeting Room Locations
Meeting Room Locations
This is a view of the 2nd Level
of the <strong>Conference</strong> Center
Room 1
Plenary
Session
Guest, Technical Tours
and Wednesday Evening
Banquet buses will
load/unload from this
area of the ACC.
River Mersey Side