ICEM11 Final Program 9.7.11pm_ICEM07 Final Program ... - Events

FINAL PROGRAM
ICEM’11
ICEM’11
The 14th International Conference
on Environmental Remediation and
Radioactive Waste Management
(ICEM)
Date: September 25-29, 2011
Location: Reims, France
Reims Champagne Congrès (RCC) Centre
ORGANIZED AND SPONSORED BY
ASME Web site: www.asmeconferences.org/icem2011
SFEN Web site: www.sfen.fr/icem-11
Andra Disposal Facility
Chooz Nuclear Power Plant

WELCOME TO ICEM’11
The Fourteenth International Conference on Environmental Remediation and Radioactive Waste
Management (ICEM’11) 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 Reims, France at the Reims Champagne Congrès (RCC) Centre.
The Environmental Engineering (EED) and Nuclear Engineering Divisions (NED) of the American Society
of Mechanical Engineers (ASME) have joined forces with the Société Française d’Energie Nucléaire (SFEN) for
ICEM’11. The conference and exhibition will offer a unique opportunity to foster cooperation and establish
contacts with participants from many countries. Conference 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’11 is expected to feature 300
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 Reims!
Conference General Co-Chairs
Anibal Taboas, for ASME (USA)
Dominique Greneche, for SFEN (FRANCE)
Honorary Co-Chairs
Mr. Christophe Behar, Nuclear Energy Director, CEA (FRANCE)
Ms. Tracy Mustin, Principal Deputy Assistant Secretary for EM, DOE (USA)
Mr. Francois-Michel Gonnot, Chairman of the Board, ANDRA (FRANCE)
Dr. Tero Varjoranta, Director, Division of Nuclear Fuel Cycle and Waste Technology, IAEA (AUSTRIA)
Mr. Arnaud Gay, Executive Vice President of the Nuclear Sites Value Development Business Unit,
AREVA (FRANCE)
Conference Managers
Gary Benda, for ASME/ICEM (USA) and Bernard Jolly, SFEN (FRANCE)
— EMERGENCY CONTACT INFORMATION —
During the conference, in case of emergency, contact Tel : +33 (0)3 26 77 44 88.
There will also be a guest message and program errata board located at the Registration Area, 1st Floor.
We would like to thank the following companies for sponsoring
the following events at the ICEM’11 Conference.
~ Our Platinum Sponsors ~
ANDRA — Tuesday Reception
URS CORPORATION — Sunday Reception
~ Our Gold Sponsor ~
WESTINGHOUSE ELECTRIC COMPANY
~ Our Silver Sponsor ~
FLUOR CORPORATION
~ Our Bronze Sponsors ~
ATOMEXPO
KRAFTANLAGEN HEIDELBERG GmbH
ONET TECHNOLOGIES

Table of Contents
ICEM’11 Corporate Sponsors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Inside Front Cover
ICEM’11 Perspectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
Background, Location and Contact Information . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
Objectives and Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
Format and Venue . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
City of Reims . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
Hotel - Accommodations. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
Restaurants - Eating out in the City of Reims . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
Foreign Exchange and Traveler’s Cheques. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
Transportation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
Insurance and Liability . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
Disclaimer . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
ICEM’11 Organizing Societies and Cooperating Int'l Agencies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
US Societies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
European Societies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
Cooperating International Agencies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
Social Events and Guest Programs. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
Sunday Golf Outing at Le Golf de Reims Champagne . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
Sunday Welcome Reception . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
Tuesday Reception . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
Wednesday Conference Banquet. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
Guest Program. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
Associated Technical Events . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
Technical Training Course . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
Technical Tours . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
Major Topics and Panel Sessions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
Major Topics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
Participating Attendees . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
Monday Morning Opening Session . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
Poster Sessions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
Special Panel Sessions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
Conference Scheduling and Additional Information . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9
Registration Hours. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9
Exhibition Hours . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9
Coffee/Tea Breaks Information. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9
Lunch Periods in Exhibit Halls Information. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9
Daily Speaker/Session Co-Chair Briefing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9
Presentation Times . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10
Conference Proceedings on CD-ROM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10
Audio Visual Office / Speaker Ready Area, Date and Time. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10
Poster Sessions Setup Date and Time . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10
Acronym List. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11
Reims City Site Map . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
Reims Train Station to Reims Champagne Congres (RCC) Centre . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
Reims Road Map and Hotel Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13
Reims Champagne Congres (RCC) Centre Maps . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14-15
Technical Program at a Glance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16-17
Technical Program Descriptions - Sessions 1 - 60 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18-34
Exhibit Hall Layout . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .38-39
Exhibitor Descriptions and Sponsorship . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40-55
Technical Abstracts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56-133
Attendee Pre-registration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 133-142
Technical Program Organizers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 143
Session Organizers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 143
Conference Steering Committee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 144
Schedule of Events . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Inside Back Cover
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ICEM’11 PERSPECTIVES
Thank you for being involved in the latest of the premier series of International Conferences on Environmental
and Radioactive Waste Management sponsored by ASME International (ASME). The final
ICEM’11 Conference Program should facilitate exchange of ideas to reduce risk, and avert the overwhelming
costs of delay in resolving environmental and radioactive waste management issues.
Meeting the high quality expectations of the event sponsors, the Societe Française d’Energie
Nucléaire (SFEN) and ASME, requires enabling contribution of: sponsors and exhibitors; dedicated volunteer
track and session chairs; and many others, from organizers to independent peer reviewers, and presen- Aníbal L. Taboas
ters. As Conference General Co-Chairs we recognize the exceptional leadership of Gary Benda (Conference
Manager) and Bernard Jolly (European Event Manager), whose intensive cooperation resulted in exceptional
planning and execution.
Our goal is to promote the necessary art, science & practice leading to sustainable global environmental
management. This includes overarching discussion to complement the plenary session key-note presentations.
Reims is specially fitting for its history as witness in evolution of the established world order.
Challenges to contemporary global order include interdependent economic imbalance, regime change,
zeal among newly-leading divergent populations, and reliance on electronic media as the primary source of Dominique Greneche
information. Volatility diverts focus from topic concepts like concerted environmental action, to insular needs (such as the nearterm
supply of food, water, and power, and security).
Industrialized nations remain as unprepared to relocate populations in response to predicted sea level changes, as they are for
the unprecedented strategic opportunity to transform the related supply and distribution of energy, food, commerce, and emerging
populations. Similarly, while the risk of sovereign debt is recognized, there is scant movement to recognize the equally obligatory
and non-discretionary nature of funding responsible environmental management. Ideological governance, however, continues
unabated, and without apparent realization that maintaining the health of wealth generating engines, particularly manufacturing
capability, is essential to sustainability.
Transitory ideologies and obstructionists successfully inflate uncertainty and perceived technical risk with tricks such as
reliance on non-rigorous or un-reproducible data, and extrapolation of performance expectations to absurd times. Projections that
significantly deviate from defensible models, theory, and observation, necessarily decrease confidence on projected results. The
misapplication of statistical methods, use of sloppy science, and the masterful use of mass communication tools, imparts plausibility
to ideological biases, and masks competence and applicability limitations.
Education imparts individual responsibility to ensure safety, advancement of technology, and to contribute to societal well-being.
Scientists, engineers, technologists, and learned societies have a unique duty to engage in discourse of public policy. Effective communication
is facilitated by simple and clear themes, such as: “Education, Energy, Environment, Economy, and National Security are
inextricably intertwined”; “Society demands to be actively aware of details that influence their reasonable expectation of an adequate
return on their investment in Governance”; and “Global partnerships are effective tools to demonstrate best-in-class performance.”
Individuals frequently feel powerless to influence global outcomes, however, success continues to favor those who properly
prepare to assess and manage risk. It is time for the technically educated to fulfill a responsibility for engagement at all levels of
government on science and technology policies affecting the public interest.
It is time to demand a return to basic principles, such as reliance on best available science, independent peer review; and
increased intellectual honesty in regulatory engineering. It is time, for example, to get past regulation of waste disposal mechanisms
according to the activity level and generating source, and to promulgate international guidelines to manage and dispose such waste
exclusively on the basis of sound multi-media risk management. It’s time to initiate transition of international efforts away from
insular engagement, and into supporting systematic approaches to inextricable factors.
Our challenge is for you to find ICEM’11 as stimulating, cost effective, and constructive, as we intend it to be, and that you
find it essential to join us for ICEM’13.
Aníbal L. Taboas
Dominique Greneche
ICEM’11 Conference General Co-Chairs

Background, Location and
Contact Information
Objectives and Background
The fourteenth International Conference 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. The
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.
Format and Venue
The ICEM’11 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
The technical program consists of an opening plenary
session and several parallel program tracks with up to
eight concurrent sessions. The sessions include 25
minute oral presentations, panels, and poster displays
which are designed to enhance dialogue between
presenters and participants.
The ICEM’11Program is divided into 60 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. The 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. The 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 six months after the conference.
City of Reims
The city of Reims is fairly small and easily walkable,
with many streets for pedestrians only. Reims, the home
of champagne (the most celebrated and celebrating
wine in the world), is the main city of the champagne
area. It is a charming city, and one that the French hold
dear to their hearts.
In Reims stands one of the most beautiful buildings of
the Middle Ages in Europe, one that is filled with
history:
Notre-Dame de Reims. The baptism of Clovis, around
the year 498, gave birth to the Kingdom of the Franks,
where the cathedral now stands. In 816 at the cathedral
took place the first royal coronation in Reims, the one
of Louis le Pious. This exceptional event explains the
choice of Reims as the coronation city. Almost all
French kings were crowned there for about 1,000 years.
Reims, and surrounding Epernay and Ay are the main
places of champagne production. Many of the largest
champagne producing houses, referred to as les grandes
marques, have their head office in Reims. Most are
open for champagne tasting and tours by appointment
only. The champagne is aged in the many chalk caves
and tunnels, some originating in the Roman period,
located deep inside the ground.
Hotel - Accommodations
ICEM has teamed with the Reims Tourism Board to
assist in room accommodations. Participants that made
arrangement through them, can reach them for any
reason. Contact: Reims Tourism Board, 12 bd du
Général Leclerc - 51722 REIMS cedex, Telephone:
03 26 77 44 74, Website: www.reims-evenements.fr.
The ICEM’11 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.
Restaurants - Eating out in Reims City Region
During the day, delegates can enjoy the numerous bars
and restaurants down the avenue from the conference
centre. During the night, come celebrate with us and
indulge in Reim’s best restaurants, cafes and bars. The
area continues to astound with new and ever evolving
imaginative food offerings which highlight the fantastic
diversity this city has to offer. If you cannot decide
where to eat check out http://www.reims-tourism.com/
which can guide you to some of the best places in the
area.
Foreign Exchange and Traveler’s Cheques
The conference secretary on-site will accept only
EUROs (no US$ or Traveler's Cheques) for payment of
any registration or optional ticket fees. Visa, American
Express, and MasterCard are also accepted.
Transportation
Transportation by Air to Reims, France
The Paris Charles De Gaulle (CDG) International
Airport provides direct access to and from major
European and North American cities and is a 50 minute
drive from Reims. Reims is also located 30 mins. from
the Paris Roissy international airport. Several
companies also offer connections to these airports.
Reims-Prunay aerodrome: Light business and tourist
aircraft or Phone: +33 (0)3 26 49 10 92
Transportation by Rail to Reims
The easiest way to get to Reims from the CDG airport
is by train. Reims is located at the junction of the Lille -
Dijon - Mediterranean and Paris - Charleville – Sedan
lines with 12 daily links between Reims-Paris. A TGV
high-speed train links Reims to Paris in 45 mins.
Travelers coming from Lille or Paris CDG airport
arrive at Champagne Ardenne TGV station, around 3
miles (5km) outside Reims. Regular local train services
connect this station to Reims city station. To consult the
times and reserve your ticket:
http://www.sncf.com/en_EN/html/ or
www.tgvesteuropeen.com.
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Transportation by Car to Reims
Reims is located at the crossroads of the A4-E50 (Paris
- Strasbourg) and A26-E17 (Calais - Troyes - Dijon)
motorways. The city has 6 motorway exits. To
determine a specific route visit: www.viamichelin.com
Insurance and Liability
All participants are encouraged to make their own
arrangements for health and travel insurance. Neither
ASME, Société Française d’Energie Nucléaire (SFEN)
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.
Disclaimer
Neither ASME or Société Française d’Energie Nucléaire
(SFEN) 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 or Société Française d’Energie Nucléaire
(SFEN). In particular, neither ASME nor Société
Française d’Energie Nucléaire (SFEN) can accept any
liability for losses arising from the provision or nonprovision
of services provided by hotel companies or
transport operators. Nor can ASME or Société Française
d’Energie Nucléaire (SFEN) 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 nor Société Française d’Energie
Nucléaire (SFEN) is able to give any warranty that a
particular person will appear as a speaker or panelist.
ICEM’11 Organizing Societies and
Cooperating International Agencies
U.S. Societies
The Environmental Engineering Division (EED) and
the Nuclear Engineering Division (NED) of ASME are
the primary organizing societies of the ICEM
conference. Since its inception in 1987, the 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’11 is also organized to support the US
Department of Energy (US DOE), the US Nuclear
Regulatory Commission (US NRC) and the US
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. The US
DOE is responsible for managing the wastes and
cleaning the sites from the past US 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
The ICEM conferences have always been conducted
jointly with a major local technical society and other
co-societies in the host country. For ICEM’11, the
Société Française d’Energie Nucléaire (SFEN) will help
partner in the organization of this conference along with
OECD (Organisation for Economic Co-operation and
Development) and the Nuclear Energy Agency.
Cooperating International 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. The International Atomic Energy
Agency (IAEA) has been assisting this conferencein
several ways. Their 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
The conference registration fee includes lunch for three
days (Monday to Wednesday), the Sunday Welcome
Reception sponsored by URS and the Tuesday
Reception sponsored by Andra. Tickets for the
Conference Banquet on Wednesday are optional and are
charged at a nominal price. Please note space is limited
and tickets will be issued on a first-come first-served
basis in EURO currency only.
Sunday Golf Outing at Le Golf de Reims Champagne
Golf de Reims Champagne is an international golf
course to the extent of professional and amateur
champions, open every day of the year. The course is
located in a sleepy village just under 10 minutes from
Reims. A group of attendees will meet and golf together
before the conference starts. Additional information can
be found at http://www.golf-dereims.com/diaporama.html
or by contacting Virgene
Mulligan, vmulligan@amrad.com.
Sunday Welcome Reception – Sponsored by URS,
Platinum Sponsor
All conference participants are invited to attend the
Welcome Reception on Sunday from 6:00pm to 8:00pm
at the RCC located by the registration area on the
second floor (“Le Bouchon” Space). Attendance is
included in the conference registration fee. Delegate
badges are required to gain entry and will be available
at the registration desk between 4:00pm - 7:00pm.
Guests are welcome but will be required to purchase a
ticket for EURO €27 plus VAT.
Tuesday Reception – Sponsored by Andra, Platinum
Sponsor
In order to celebrate Andra's 20th Anniversary, Ms.
Marie-Claude Dupuis, Chief Executive Officer is pleased
to invite all of the participants of ICEM 2011 to a buffet
on Tuesday evening, 27 September 2011. This reception
is sponsored by Andra for all registrants and will be held
from 6:00pm to 8:00pm in the Exhibit Hall. Delegate

adges are required to gain entry and guests are welcome
but will be required to purchase a ticket for EURO €27
plus VAT at the registration desk prior to this event.
Please take this opportunity to review, evaluate and test
the current products and services of the exhibiting
companies. They look forward to seeing everyone there
to celebrate this anniversary.
Wednesday Conference Banquet
The entertainment hallmark of the ICEM conference is
the traditional and culturally festive banquet, reflective
of the host country. This year’s ICEM 2011 Banquet
will be held at the Champagne De Castelnau Caveau
from 7:30pm to 11:30pm. A four course meal with four
different champagnes will be served. The ICEM
Conference Banquet is an optional extra, but truly
memorable. Tickets and badges will be required to gain
entrance. Please note: This event is not included in the
purchase price of your registration fee, there is an
additional nominal cost to attend this event. Guests are
also welcome to attend this event. For our fully paid
conference registrants: EURO €54 plus VAT and for our
Guests: €67 plus VAT.
Guest Program
ICEM will sponsor a Guest Welcome Reception, hosted
by Ms. Dianne Benda on Monday morning at 8:00am in
Room 1 on Level 2. This “Guest Welcome Reception”
will review all of our scheduled tour options available.
While there will be tourism information available
throughout the event, we encourage you to attend to
answer questions and assist you in planning your week
in Reims and its surrounding areas to make the most of
your visit.
You must arrive at least a half hour prior to the
scheduled departure time of that scheduled tour. All
Tours unless otherwise noted are accompanied by an
English Speaking guide and will depart from and return
to the RCC, registration area on the 1st floor. Upon
availability, last minute tickets can be purchased. Only
EURO currency will be accepted.
Day Tour to Paris (Guided Tour #1)
Sunday, 25th September, 9:00am-5:-00pm,
135 € + VAT
On Sunday, we are organizing a group to travel by train
from Reims to Paris and enjoy a brief time in the local
area. At the Paris East train station, we will board a Hop
On – Hop Off bus for a 4 hour quick city tour. We will
hop off at Notre Dame, The Eiffel Tower and at the
Place d’Concorde and you will be able to have lunch on
one of the stops on your own. After our tour of the
highlights of Paris we will re-board the train at 4:00pm
in time to return to the RCC for the Sunday reception.
Cost includes roundtrip train, escort and tour bus. The
group will meet on Sunday at the Best Western Hotel at
8:15am and later at the Reims Train Station at 8:45am.
Walking Tour of Reims (Guided Tour #2A)
Monday, 26th September, 9:00am – 12:00pm,
25 € + VAT
(Note: This tour is also available on Thursday, 2:15 –
6:00 as Guided Tour #5)
Circus School, Paris and Mars Gates, Forum and
Royal Square, Notre Dame with Guide. Sights
include;
• Hard Built Circus and Riding School - 19th
century, now renovated and used for shows
• The Paris Gate - built for the coronation of Louis
XVI in 1775
• The Gate of Mars - one of the four arches built ca.
200 AD to mark the four main thoroughfares of
Durocortorum, capital of the Roman province of
Belgica.
• The City Hall - typical of 17th century
architecture. The facade bears an equestrian statue
of King Louis XIII in its centre
• The Forum Square - located on the site of the
antique forum, this square was the market place,
Gallo-roman Cryptoporticus (semi-subterranean
gallery) and the Le Vergeur House Museum,
• The Royale Square - ca. 1760, the square was
built by the population as a tribute to Louis XV. In
its centre, stands a statue of the king surrounded by
a series of symbolic decorative figures by Pigalle.
• The Notre-Dame Cathedral - a master-piece of
gothic art, the Cathedral of Our Lady was started in
1211. It was the Cathedral of the Coronations for
French Kings in memory of the baptism of Clovis
by Saint Remi on Christmas Day 498.
Walking Tour of Reims / Champagne Cellars Tour
(Guided Tour #2B)
Monday, 26th September, 2:15pm – 6:00 pm,
43 € + VAT
The Basilica St-Remi and Champagne Cellars Taittinger,
with Guide. Sights include;
• Basilica Saint-Remi - The largest Romanesque
pilgrimage church in northern France. It was built
as a shrine to Saint Remi. The nave was
consecrated in 1049 whereas the apse was built in
the late 12th century.
• Visit of Champagne Cellars – Taittinger -
Located in the heart of Reims, between City Hall
and the Cathedral, the Demeure des Comtes de
Champagne makes the historical heritage of the
city. Built in the 13th century, and partially
destroyed during the First World War, it was
restored under the direction of the Fine Arts
Ministry. The tour will be concluded by a
Champagne tasting. Price includes entrance fee to
the champagne house.
Visit of the Champagne Vineyard by Coach with
Lunch (Guided Tour #3)
Tuesday, 27th September, 9:30am – 5:00pm,
97 € + VAT
Cruise near Epernay on the Marne River.
• Travel through the Champagne Vineyards - For
the past three centuries, the passion of the men of
Champagne and their respect for local traditions
have resulted in the exceptional wines that are
famous around the world for their subtle and
delicate bouquet.
• Meeting at Cumieres for Lunch Cruise - The
jetty is located in the small village of Cumieres,
near Epernay. You will sail on a sternwheeler
between the vineyard covered slopes and the viticol
villages nested on hillsides. After the lock, different
species of birds will escort you to the doors of the
Valley of the River Marne. All the history of the
region seems to spring at each turn of the river: the
castle of the famous Veuve Clicquot, Dom
Perignon, the revolt of the wine-growers in 1911,
the Duchess of Uzes, and so on.
5

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• End Of The Cruise And Travel To Hautvillers
Village - On the outskirts of Epernay, a small
village known around the world thanks to a
Benedictine monk named Dom Perignon, is
perched on sunny vine planted hillsides. The
legend of Dom Perignon adds an intangible but no
less genuine aura to Hautvillers. He is said to have
been able to make a “grey” or red still Champagne
wine into a sparkling wine of perfect clarity. Dom
Perignon is buried in the village church. The tour
will include a champagne toasting.
The Old City of Troyes and Shopping Outlet by
Coach (Guided Tour #4)
Wednesday, 28th September, 9:00am -5:30pm,
85 € + VAT
• Troyes - Travel by bus to see the Champagne Fairs
and the Saint-Jean-au- Marche quarter. It is mainly
in the urban fabric that the memory of the great
Champagne Fairs can be found, fairs that were held
in the city of Troyes during the festival of Saint
Vincent and Saint Remi. The confusion of streets
and small squares with closed courtyards give an
idea of the city at this period.
• Cathedral of Saint Peter and Saint Paul - This
cathedral was built between the 13th and 15th
centuries and is characteristic of the Gothic style.
Only the Saint Peter tower was completed - the
Saint Paul tower has remained unfinished since
1545.
• The Saint-Pantaleon Church, the Parish of the
Polish Community of Troyes - Built on the site of
a synagogue (according to tradition), a genuine
museum of 16th century Troyes statuary, since it
was the hiding place for statues saved during the
French Revolution. Some were created by
Dominique le Florentin, an artist from Troyes and
decorator for Francois 1st.
• Shopping - Factory and Trade Outlets - Troyes
Designer Outlet - The first of McArthurGlen’s
discount outlet malls in France, having opened in
1995. It’s not surprising that McArthurGlen chose
this city as the location for their designer outlet as
Troyes’ association with textile manufacture and
knitting go back to the 12th century. The Marque
Avenue and Marques City outlets will also be
visited. Here you’ll find 210 top fashion names.
Walking Tour of Reims / Champagne Cellars Tour
(Guided Tour #5)
Thursday, 29th September, 2:15pm – 6:00pm,
43 € + VAT
The Basilica St-Remi and Champagne Cellars Taittinger
with Guide. This is the same tour as Monday afternoon
Tour #2B, but provides the attendee in sessions all week
a second opportunity to see and taste at little of Reims
and the Champagne region.
Associated Technical Events
Technical Training Course
RISK REDUCTION IN REMEDIATION, WASTE
MANAGEMENT AND DECOMMISSIONING
Sunday: 9:00am-4:00pm Room: 5
The workshop is being held as a service to the ICEM
community and is relevant to all technical program
attendees as well as other professionals in the nuclear
field. This workshop is intended as a condensed but
intense training in the subject area of risk reduction for
nuclear remediation, radioactive waste management and
decommissioning of nuclear reactors and facilities.
Participants will receive a certificate of training
completion. Professional education credits may be
available from ASME, IHMM or other organizations.
Topics covered will include risk assessment, risk
reduction methodologies, risk vs. cost, and practical
lessons from various projects. Technical experts from
the industry and senior leaders from international
organizations will be invited as lecturers. The workshop
will be directed by Dr. Jas Devgun.
The agenda consists of six hours of intense instruction
with a one hour lunch break. Refreshments for coffee
breaks will be provided.
Technical Tours
Three technical tours are planned to see Andra and
Chooz D&D project radioactive waste management
programs first hand. The tours will take place
immediately after the conference on Friday. Please
Note: Tours will depart on Friday at 7:00 am at the
RCC centre.
1. Reims to Andra, LLW Site Tour (Tour 1A)
• The Disposal Facilty for Low-Level and
Intermediate-Level (LIL) Waste
• The Disposal Facility for Very-Low-Level (VLL)
Waste
2. Reims to Andra, HLW Site Tour (Tour 1B)
• The Underground Laboratory
• Saudron' s Technological Centre
3. Reims to Chooz, D&D Technical Tour (Tour B)
Major Topics and Panel Session
Major Topics
The ICEM11 Technical Program is divided into 60
technical sessions conducted over three and one-half
days. A listing of the specific sessions within each of
the five technical programs can be found in the
“Program at a Glance” Section.
Participating Attendees
Over 400 abstracts have been accepted from more than
30 countries, including submittals from Western
Europe, Central and Eastern Europe, the Far and
Middle East, North and South America and Australia.
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.
The 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.

Monday Morning Opening Session
SESSION 1 - PLENARY - OPENING SESSION
Monday: 9:00am -12:30pm Room: Salle Royale
The Opening Session will begin Monday morning with
the keynote presentations setting the theme for this
year’s conference. Coffee will be served on the 2nd
floor Foyer from 08:00 until the program begins at
9:00am.
A break is scheduled after the third speaker.
The Welcome speakers and Keynote speakers are:
• Mr. Christophe Behar, Nuclear Energy Director,
CEA (France)
• Ms. Tracy Mustin, Principal Deputy Assistant
Secretary for EM, DOE (USA)
• Mr. Francois-Michel Gonnot, Chairman of the
Board, Andra (France)
• Dr. Tero Varjoranta, Director, Division of
Nuclear Fuel Cycle and Waste Technology, IAEA
(Austria)
• Mr. Arnaud Gay, Executive Vice President of the
Nuclear Sites Value Development Business Unit,
AREVA (France)
Special Panel Sessions
Listed below is a brief summary on the ICEM2011
panels. A more comprehensive and detailed description
and the panelists are listed in the Technical Program
section with each Session.
Poster Sessions
The conference technical program will contain three
major Poster Sessions on Monday - Wednesday
arranged from the five Technical Tracks. The leading
objective for the poster sessions is to provide a forum
for experts in the field and interested attendees to gather
in the RCC where they can move around freely and
engage in discussions, which would normally not be
possible during the oral sessions. The three best Posters
from each Track will be displayed on Thursday
morning.
SESSION 2: APPROACHES FOR
INTERNATIONAL COLLABORATION (5.18)
Monday: 1:45pm - 6:00pm Room: 1
An important element to reducing the cost and schedule
of a country’s and/or organization’s environmental
remediation mission is forming key international
collaborative partnerships that focus on identifying and
leveraging international expertise, infrastructure, and
collaboration opportunities. This panel will provide an
overview of the different approaches and initiatives
used to promote international collaboration in
environmental remediation and/or radioactive waste
management, with a focus on the challenges and
opportunities unique to each country and/or
organization.
Panelists Include: Mark Butez, Andra (France);
John Mathieson, NDA (UK); Ian Bainbridge, AECL
(Canada); Jong-Kil Park, KHNP (Korea);
Malgorzata K. Sneve, Norwegian Radiation Protection
Authority (Norway)
SESSION 3: LESSONS LEARNED: FUKUSHIMA,
CHERNOBYL-25 YEARS LATER, TMI-2 &
OTHER EXPERIENCES (3.11)
Monday: 1:45pm - 6:00pm Room: Salle Royale
This panel was initially planned to discuss confinement
activities and lessons learned from Chernobyl at a time
of 25th anniversary of the Chernobyl accident (April
26, 1986), lessons from TMI-2 accident (March 28,
1979) and other industry experience with smaller
events. However, the natural events of March 11, 2011
(large earthquake and tsunami) led to the accident at the
Fukushima- Dai-ichi complex which has been given the
highest rating of seven on the international scale,
equivalent to that of the 1986 Chernobyl crisis. The
recovery efforts at Fukushima are still ongoing. This
panel will discuss lessons learned from Fukushima,
Chernobyl, and TMI-2 related to recovery, confinement,
decommissioning, and future design lessons.
Panelists Include: Dr. Tero Varjoranta, IAEA
(Austria); Sergii Mitichkin, Chernobyl NPP (Ukraine);
Thomas Chauveau, Bouygues-Construction (France);
Didier Dall’ava, CEA/DEN/DADN (France);
Svetlana Bratskaya, Institute of Chemistry of Russian
Academy of Science (Russia); Dominique Greneche,
SFEN (France); and Claudio Pescatore, OECD/NEA
(France)
SESSION 10: EMERGING ISSUES IN THE
MANAGEMENT OF I/ILW (1.16)
Tuesday: 8:30am - 12:30pm Room: 1
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. There will be discussion on large,
disused components that are part of the
decommissioning L/ILW waste stream. The
engineering of facilities for the disposal of all such
wastes should be proportionate to the long-term
environmental impact that might arise.
Panelists Include: Irena Mele, Section Head of Waste
Technology, IAEA (Austria); Keith McConnell,
Deputy Director, US NRC (USA); Bruno Cahen,
Director, Andra (France); Geraldine Dandrieux, Head
of Waste, Research Facilities and Fuel Cycle Facilities
Department (France); Kazuyuki Kato, Federation of
Electric Power Companies (Japan); Paul Dixon, Los
Alamos National Lab (USA); and Dick Raaz, Chairman
and Director, UK LLWR (UK)
SESSION 11: HOW CAN NETWORKS IMPROVE
THE IMPLEMENTATION OF ER PROJECTS?
THE IAEA NETWORK ON ENVIRONMENTAL
MANAGEMENT AND REMEDIATION-
ENVIRONET (4.15)
Tuesday: 8:30am-12:30pm Room: 4
Environmental remediation projects tend to be
constrained by several aspects being the lack of
financial resources one of the most prominent factors.
However, even when financial resources are available
lack of institutional framework (e.g. lack of
regulations), lack of human resources, and absence of a
solid technical basis at the national level will contribute
to slow the pace of implementation. Networking intends
to bring problem holders and solution donors together
7

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and enhance the exchange of experience while fostering
the construction of partnerships. The ENVIRONET was
initially presented to the international community at
WM 2010. The ICEM 2011 will be an opportunity to
present its achievement, broaden its affiliation and build
an agenda of activities for the next years.
Panelists Include: Leo van Velzen, NRD
(Netherlands); Peter Booth, WSP Group (UK); and
joining after the break - Irena Mele, Section Head of
Waste Technology, IAEA (Austria)
SESSION 20: CHALLENGES WHEN SELECTING
DISPOSAL OPTIONS IN THE LIGHT OF THE
NEW IAEA CLASSIFICATION SCHEME (1.17)
Tuesday: 1:45pm - 6:00pm Room: 1
The new IAEA classification scheme is based on long
term safety – primarily disposal. The potential options
for disposal include: above surface engineered landfill,
near surface disposal (trenches, vaults or shallow
boreholes), engineered facilities at intermediate depth
(10s to 100s of meters) and geological disposal (> few
hundred metres). Specific waste types will need specific
consideration (e.g. disused sealed sources, graphite
waste, and radium bearing waste). National schemes
will be circumstance dependent.
The following will be discussed:
• Near surface or geological disposal for SL-LILW
• Separate disposal for SL-LILW and VLLW
• Advantages and disadvantages of opting for codisposal
• Borehole disposal as potential solution for the
countries having limited waste inventories
• Feasible approaches for disposal of low level longlived
waste
This panel will provide a forum for the exchange of
scientific and technical information on disposal of
different categories of radioactive waste with focus on
current approaches.
Panelists Include: Linde Nel, Director of Operations
and Maintenance Services (South Africa); Vaclav
Hanusik, Senior Researcher, VUJE (Slovak Republic);
Dr. Irina Gaus, Senior Expert (Switzerland); Thibaud
Labalette, Program Director at Andra (France); Balint
Nos, Head of Strategy Development and Engineering
Office of PURAM (Hungary); Dr. Peter Brennecke,
Bundestamt fur Strahlenschutz (BFS), Retired
(Germany); Dr. Kazumi Kitayama, Senior Technical
Advisor, Nuclear Waste Management Organization of
Japan (NUMO) (Japan); and Keith McConnell,
Deputy Director, US NRC (USA)
SESSION 21 & 22: CONTRIBUTION AND
COMPLEMENTARITIES OF INTERIM
STORAGE, GEOLOGICAL DISPOSAL,
PARTITIONING & TRANSMUTATION
REVERSIBILITY REGARDING GLOBAL
OPTIMIZATION OF RADWASTE
MANAGEMENT (2.15)
Tuesday: 1:45pm-3:30pm Room: 4
Tuesday: 4:15pm-6:00pm Room: 4
Session 21 is a two part panel in conjunction with
Session 22. The first part will consist of a introductory
paper and then a panel will address the status of HLW
and Spent Fuel interim storage, processing and national
programs. Partitioning and transmutation are also
investigated in several countries. Interim storage is
required to accommodate waste as long as sustainable
management solutions are not available and interim
storage duration up to 100 years has been often
considered.
Speakers Include: Bernard Boullis, CEA (France);
Wilhelm Bollingerfehr, DBE (Germany); Philippe
Lallieux ONDRAF (Belgium); Claudio Pescatore,
NEA, (France); Jean-Michel Hoorelbeke, Andra
(France); Farok Sharif, URS (USA); Jürg Schneider,
NAGRA (Switzerland); and Neil Smart, NDA (UK)
SESSION 29: INTERNATIONAL
COOPERATION: NEA ROAD MAP, HOW TO
INCREASE SYNERGY (3.12)
Wednesday: 8:30am-12:30pm Room: 1
This session will start with short presentations and
conclude with a panel session.
The session will end with a panel discussions
moderated by Ivo Tripputi (Sogin).
Panelists include: Juan Luis Santiago (Enresa), Jim
Marra (US DOE), and Gerard Laurent
(EDF/CIDEN)
SESSION 38: YOUNG GENERATION NETWORK
(YGN) AND PROFESSIONAL DEVELOPMENT
PROGRAMS (5.17)
Wednesday: 10:45am - 12:30pm Room: 5
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 International 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.
For the session we conduct ‘An audience with…….’
where two leaders of industry provide candid views of
their career paths and offer advice to young
professionals answering any questions and providing
advice on career development.
Panelists Include: Sarah Greenwood, AREVA (UK);
and Jim Blankenhorn, Permafix Environmental
Services Inc.; and Claudio Pescatore, OECD/NEA
(France)
SESSION 48: RADIUM REMEDIATION -
HISTORICAL PERSPECTIVES AND CURRENT
CIRCUMSTANCES - PART 3 OF 3 (4.13)
Wednesday: 4:15pm - 6:00pm Room: 1
An international panel will discuss and compare
progress and history of national radium remediation
programs. Lessons learned will be featured and shared.
The outlook for the final closure on this issue
worldwide will also be addressed. The perspectives and
panelists invited include those from practitioners in
government policy leadership, regulatory oversight and
licensing, health and safety impacts and protection,
environmental remediation practice and affected
community stakeholders.
Panelists Include: Stéphane Pepin, FANC (Belgium);
Keith McConnell, USNRC (USA); Jean-Luc
Lachaume, ASN (France); and Steve Brown, SENES
Consultants Ltd. (USA)

SESSION 49 AND 50: COMMUNICATIONS AND
KNOWLEDGE MANAGEMENT - PART 1 OF 2
(5-21)
Wednesday: 1:45pm - 3:30pm Room: 4
Wednesday: 4:15pm - 6:00pm Room: 4
This is a two part series of paper presentations and a
following panel session discussion on communications
and knowledge management. Current efforts and views
will be presented during this first session. This session
is directly followed by the second part, Panel Session
#50. Presenters will each provide a 10-15 minute
overview to the audience before the break, and will then
resume on this topic.
Panelists Include: Laurie Judd, NuVision
Engineering (USA); Leonel Lagos, Florida
International University (USA); Yanko Yanev, IAEA
(Austria); Hitoshi Makino, JAEA (Japan); Bill
Shingler, Fluor Government Group (USA) and Herve
Bienvenu, Andra (France)
Conference Scheduling and
Additional Information
Registration Hours
DAY / DATE TIME
Sunday, September 25, 2011 4:00pm to 7:00pm
Monday, September 26, 2011 7:15am to 6:00pm
Tuesday, September 27, 2011 7:15am to 6:00pm
Wednesday, September 28, 2011 7:15am to 6:00pm
Thursday, September 29, 2011 7:15am to 12:30pm
Exhibition Hours
DAY / DATE TIME
Monday, September 26, 2011 12:00pm to 6:00pm
Tuesday, September 27, 2011 8:30am to 8:00pm
Wednesday, September 28, 2011 8:30am to 5:00pm
Thursday, September 29, 2011 8:30am to 11:00am
Coffee/Tea Breaks
Complimentary coffee and tea will be served for all
meeting participants at 8:00 am, during the morning
breaks and the afternoon breaks each day of the
conference.
Coffee/Tea Break Schedule
DAY / DATE / TIME LOCATION
Monday, September 26, 2011 RCC - 2nd Floor
8:00am - 9:00am “Le Bouchon” Space
Monday, September 26, 2011 RCC - 2nd Floor
After Third Speaker “Le Bouchon” Space
Monday, September 26, 2011 RCC - Exhibition Hall
3:30pm - 4:10pm 1st Floor
Tuesday, September 27, 2011 RCC - Exhibition Hall
10:15am - 10:40am &
3:30pm - 4:10pm
1st Floor
Wednesday, September 28, 2011 RCC - Exhibition Hall
10:15am - 10:40am &
3:30pm - 4:10pm
1st Floor
Thursday, September 29, 2011 RCC - Exhibition Hall
10:15am - 10:40am 1st Floor
Lunch Periods
Lunch will be served in the Exhibit Hall on Monday,
Tuesday and Wednesday. Lunch serving hours are from
12:30-1:15 pm. 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 can be found at
http://www.reims-tourisme.com/a copy of which will be
given to delegates upon arrival.
Lunch Periods
DAY / DATE / TIME LOCATION
Monday thru Wednesday RCC - Exhibition Hall
12:30pm - 1:30pm 1st Floor
Thursday
On your own
N/A
Daily Speaker/Session Co-Chair Briefing
Monday thru Thursday Mornings: 7:30am - 8:00am
RCC, Room: “Le Millesime” Space, 1st Floor
A morning briefing will be provided to all Speakers,
Panelists, Poster Presenters, and Session Co-Chairs on
the day of their session. The briefing will include
coffee/tea and will be served at the conference center.
Most hotels have breakfast included in the cost of the
room, but the speaker’s briefing will give you the time
for final arrangements before your session. The
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.
9

10
Presentation Times
The below 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. The 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.
Approximate Presentation Times
AM START TIME PM START TIME
Session Start 8:30 Session Start 1:45
Paper 1 8:35 Paper 1 1:50
Paper 2 9:00 Paper 2 2:15
Paper 3 9:25 Paper 3 2:40
Paper 4 9:50 Paper 4 3:05
Break 10:15-10:40 Break 3:30-4:10
Session Start 10:45 Session Start 4:15
Paper 5 10:50 Paper 5 4:20
Paper 6 11:15 Paper 6 4:15
Paper 7 11:40 Paper 7 5:10
Paper 8 12:05 Paper 8 5:35
Session Ends 12:30 Session Ends 6:00
Lunch Break 12:30-1:40
Conference Proceedings on CD-ROM
Each conference registrant will receive the conference
proceedings on a CD-ROM mailed approximately six
months after the conference. Additional proceedings
may be ordered at an additional charge, by writing to
the ASME Order Department, 22 Law Drive, P.O. Box
2300, Fairfield, NJ 07007-2300, U.S.A., Telephone 1-
800-THE-ASME.
AV Office / Speaker Ready Area
The AV Office / Speaker Ready area will be available
for speakers to load and review their PowerPoint slides.
This area will be open Sunday from 4:00pm - 7:00pm,
Monday thru Wednesday from 7:15am - 5:00pm, and
Thursday from 7:15am - 12:30pm at the RCC Centre in
the Salle De Presse on the 2nd Floor. The on-site
loading schedule of PowerPoint presentations are listed
below.
Coffee/Tea DAY / DATE Break / TIMESchedule LOCATION
Sunday — 3:00pm-7:00pm
Loading All Power Points All Sessions 1-60
Monday — 9:00am-12:30pm
Reserved for Loading
Monday Afternoon Sessions Sessions 2-9
Monday — 2:00pm-5:00pm
Loading All Power Points Sessions 10-60
Tuesday — 9:00am-12:30pm
Reserved for Loading
Tuesday Afternoon Sessions Sessions 20-28
Tuesday — 2:00pm-5:00pm
Loading All Power Points Sessions 29-60
Wednesday — 9:00am-12:30pm
Reserved for Loading
Wednesday Afternoon Sessions Sessions 40-49
Wednesday — 2:00pm-5:00pm
Loading All Remaining Power Points Sessions 50-60
Poster Session Setup Date and Time
Poster Presentations will be located in the Exhibit Hall
on Level 1 of the Conference Center. Each day of the
conference a Q&A time is set up to meet with the
Poster Presenters. At the end of each session there will
be three Poster Presentations selected as “Best of
Show”. These winning selections will remain until the
end of the conference. We ask that you check back each
day for these selections and on Thursday to view all of
the awardees.
Day Monday Tuesday Wednesday Thursday
Session # 9 19 39 A/B/C 60
Poster 8:00 - 8:00 - 8:00 - Best of
Setup 12:00 8:30 8:30 Show
Poster 12:00 - 8:30 - 8:30 - 8:30 -
Period 5:45 5:45 5:45 11:00
Q&A 12:30 - 10:15 - 10:15 - x
Period 1:30 10:40 10:40
Q&A 3:30 - 3:30 - 3:30 - x
Period 4:10 4:10 4:10
Poster 5:45 - 5:45 - 5:45 - 11:00 -
Removal 6:00 6:00 6:00 12:30

Acronym List
AEA Atomic Energy Agency
ALARA As Low As Reasonably Achievable
ANDRA Agence nationale pour la gestion des
déchets radioactifs
ASME American Society of Mechanical Engineers
BWR Boiling Water Reactor
CEA Commissariat à l’Energie Atomique et aux
Energies Alternatives
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 International Atomic Energy Agency
IDN International 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
Notes
________________________________________________
________________________________________________
________________________________________________
________________________________________________
________________________________________________
________________________________________________
________________________________________________
________________________________________________
________________________________________________
________________________________________________
________________________________________________
________________________________________________
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
OECD Organization for Economic Cooperation &
Development
PRA Probabilistic Risk Analysis
PWR Pressurized Water Reactor
R&D Research & Development
RCC Reims Champagne Congrès Centre
RCRA Resource Conservation and Recovery Act
RH-TR Remote Handled Transuranic Waste
ROC Republic of China
RPV Reactor Pressure Vessel
RW Rad Waste
SFEN Société Française d’Energie Nucléaire
SNF Spent Nuclear Fuel
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 Symposium
WNA World Nuclear Association
Notes
________________________________________________
________________________________________________
________________________________________________
________________________________________________
________________________________________________
________________________________________________
________________________________________________
________________________________________________
________________________________________________
________________________________________________
________________________________________________
________________________________________________
11

12
Reims City Site Map
RCC
Wednesday Banquet
Champagne de Castelnau Caveau
5 rue Gosset
Reims Train Station to Reims
Champagne Congrès (RCC) Centre (15 minute walk)

Reims Road Map and Hotel Locations
Wednesday Banquet
Champagne de Castelnau Caveau
5 rue Gosset
# HOTEL NAME / ADDRESS
3 Grand Hotel des Templiers / 22 rue des Templiers, 51100 Reims
4 Kyriad Reims Center / 7‐9 rue du Général Sarrail, 51100 Reims
5 Grand Hotel Continental / 93 Place Drouet Erlon, 51100 Reims
6 Holiday Inn Garden Court / 46 Rue Buitrette, 51100 Reims
7 Mercure Cathedrale Hotel / 31 Boulevard Paul Doumer, 51100 Reims
11 Best Western – Hotel de la Paix / 9 rue Buirette, 51100 Reims
12 Hotel Porte Mars / 2 place de la République, 51100 Reims
13 Quality Hotel / 37 Boulevard Paul Doumer, 51100 Reims
14 Grand Hotel de l’Univers / 41 Boulevard Foch, 51100 Reims
16 Bristol Hotel / 76 place Drouet d’Erlon, 51100 Reims
20 Hotel Crystal / 86, place Drouet d’Erlon, 51100 Reims
21 Hotel du Grand Nord / 75 Place Drouet, 51100 Reims
22 Express by Holiday Inn / Boulevard Paul Doumer 21, 51100 Reims
23 Ibis Centre Reims / 28 boulevard Joffre, 51100 Reims
28 Suite Hotel / 1 rue Edouart Mignot, 51100 Reims
29 Résidence Clairmarais / 25 Rue Edouard Mignot, 51100 Reims
13

14
Convention Center — Level 0 (Entrance Access)

Convention Center — Level 1 & Level 2
Level 1 — Registration, Exhibits, Poster, and Speaker’s Briefings
A
B
Lounge Area
C
A – Registration/Speaker & Co-Chair Check-In,
B – Poster Area, C – Speaker's Briefing
Level 2 — Opening Sessions and All Technical Sessions
1
2
3
4
5
6
10
D
E
D – Opening Session
1-10 – Technical Session Rooms
E – Sunday Welcome Reception/ Monday Morning Break Area
15

SESSION #
16
Technical Program at a Glance
SESSION TITLES
MONDAY AM - SEPTEMBER 26, 2011
1 Opening Session • • • • • Salle Royale 9:00
MONDAY PM - SEPTEMBER 26, 2011
2 PANEL: Approaches for International Collaboration • Room 1 1:45
3 PANEL: Lessons Learned: Chernobyl 25 Years Later, TMI & Other Experiences • Salle Royale 1:45
4 National and International Programs for L/ILW Management • Room 2 1:45
5 L/ILW Treatment Technology Development and Implementation • Room 3 1:45
6 Issues and Solutions Related to Spent Fuel, TRU, and HLW Transportation and Disposal • Room 4 1:45
7 National and International ER Programs • Room 5 1:45
8 Experiences in ER Clean-Up Methods and Actions • Room 10 1:45
9 POSTER SESSION: Low/Intermediate Level Waste Management Posters • Exhibit Hall 12:00
TUESDAY AM - SEPTEMBER 27, 2011
10 PANEL: Emerging Issues in the Management of I/ILW • Room 1 8:30
11 PANEL: IAEA: How can Networks Improve the Implementation of ER Projects? • Room 4 8:30
12 Waste Minimization, Avoidance, and Recycling • Room 2 8:30
13 HLW, Fissile, TRU and Spent Fuel Short and Long-Term Storage Issues • Room 3 8:30
14 D&D of Power Reactors and Research Reactors • Room 5 8:30
15 The French D&D Activities - Organization, Strategy, Objectives and Experience • Room 10 8:30
16 National and International D&D Programs • Room 10 10:45
17 Applying Strategic Planning, Decision-Making and Risk Reduction Methodologies in EM • Room 6 8:30
18 Economic Analyses, Monitoring Strategies and Project Management in EM • Room 6 10:45
19 POSTER SESSION: Spent Fuel, Fissile, Transuranic and HLW Management Posters • Exhibit Hall 8:30
TUESDAY PM - SEPTEMBER 27, 2011
20 Challenges When Selecting Disposal Options in the Light of the New IAEA Classification Scheme • Room 1 1:45
21 PANEL: Interim Storage, Geological Disposal, Partitioning & Transmutation • Room 4 1:45
22 PANEL: Interim Storage, Geological Disposal, Partitioning & Transmutation Issues • Room 4 4:15
23 Advanced L/ILW Conditioning Technologies - Part 1 of 2 • Room 2 1:45
24 L/ILW Waste Characterization, Assay, and Tracking Systems - Part 1 of 2 • Room 2 4:15
25 D&D of Non-Reactor Nuclear Facilities • Room 3 1:45
26 D&D Technologies - Part 1 of 2 • Room 5 1:45
27 ER Site Characterization and Monitoring - Part 1 of 2 • Room 10 1:45
28 Public Perception Issues and Stakeholder Engagement Strategies in Radioactive EM • Room 6 1:45
WEDNESDAY AM - SEPTEMBER 28, 2011
29 PANEL: International Cooperation: NEA Road Map, How to Increase Synergy • Room 1 8:30
30 Siting, Design, Construction, and Operation of L/ILW Disposal Facilities - Part 1 of 2 • Room 2 8:30
31 L/ILW Waste Characterization, Assay, and Tracking Systems - Part 2 of 2 • Room 3 8:30
LLW
HLW
D&D
ER
EM
ROOM #
TIME

SESSION #
Technical Program at a Glance
WEDNESDAY AM - SEPTEMBER 28, 2011
32 Repository Programs: - Part 1 of 2 • Room 4 8:30
33 Recent Advances in Processing and Immobilization of HLW, Fissile Material and
Transuanic (TRU) - Part 1 of 2 • Room 6 8:30
34 Uranium Sites, ER Issues, Site Characterization and Monitoring - Part 2 of 2 • Room 10 8:30
35 Merged with Session 34
SESSION TITLES
36 Radium Remediatio:- Historical Perspectives and Current Circumstances - Part 1 of 3 • Room 10 10:45
37 Young Generation Network (YGN) and Professional Development Programs - Presentations • Room 5 8:30
38 Young Generation Network (YGN) and Professional Development Programs - Meeting • Room 5 10:45
39A POSTER SESSION: D&D • Exhibit Hall 8:30
39B POSTER SESSION: ER • Exhibit Hall 8:30
39C POSTER SESSION: EM & Crosscutting • Exhibit Hall 8:30
WEDNESDAY PM - SEPTEMBER 28, 2011
40 D&D Management Approaches and Planning Tools • Room 2 1:45
41 D&D Technologies - Part 2 of 2 • Room 3 1:45
42 Liquid Waste Treatment Process and Experience • Room 5 1:45
43 Siting, Design, Construction, and Operation of L/ILW Disposal Facilities - Part 2 of 2 • Room 6 1:45
44 Disposal Site and Waste Form Characterization and Performance Assessment - Part 1 of 2 • Room 6 4:15
45 Repository Programs: - Part 2 of 2 • Room 10 1:45
46 National and International Programs for Spent Fuel, Fissile, TRU, and HLW Management • Room 10 4:15
47 Radium Remediation - Historical Perspectives and Current Circumstances - Part 2 of 3 • Room 1 1:45
48 PANEL: Radium Remediation Historical Perspectives and Current Circumstances - Part 3 of 3 • Room 1 4:15
49 PANEL: Communications and Knowledge Management - Part 1 of 2 • Room 4 1:45
50 PANEL: Communications and Knowledge Management - Part 2 of 2 • Room 4 4:15
THURSDAY AM - SEPTEMBER 29, 2011
51 Safety Considerations Associated with L/ILW Management • Room 2 8:30
52 Disposal Site and Waste Form Characterization and Performance Assessment - Part 2 of 2 • Room 3 8:30
53 Global Partnership in Environmental Management - Part 1 of 2 • Room 1 8:30
54 Global Partnership in Environmental Management - Part 2 of 2 • Room 1 10:45
55 Safety and Security Related to Environmental and Nuclear Materials Management • Room 4 8:30
56 Advanced L/ILW Technologies - Part 2 of 2 • Room 4 10:45
57 Recent Advances in Processing and Immobilization of HLW, Fissile and TRU - Part 2 of 2 • Room 5 8:30
58 D&D Radiological Characterization and Monitoring • Room 10 8:30
59 Risk/Performance Assessments and Contaminant Migration • Room 6 8:30
60 POSTER SESSION: Best Posters of ICEM2011 • • • • • Exhibit Hall 8:30
LLW
HLW
D&D
ER
EM
ROOM #
TIME
17

Monday AM Technical Sessions
Presentations with a paper prepared for the post conference CD are
noted as “wP”. Presentations without papers are noted as “w/oP”.
Authors and Panelists speaking are shown in Bold. Coffee will be
served at 8:00am, Tuesday - Thursday in Lounge A in the Exhibit Hall.
SESSION 1
Monday: 9:00am -12:30pm Room: Salle Royale
PLENARY SESSION
Co-Chairs: Yvette Collazo, US DOE (USA)
Dominique Grenêche, SFEN (France)
The Opening Session will begin Monday morning with the keynote
presentations setting the theme for this year’s conference. Coffee will
be served on the 2nd floor Foyer from 08:00 until the program begins
at 9:00am.
• Welcome to the ICEM’11 Conference —
Yvette Collazo, for ASME (USA)
• Welcome to Reims —
Dominique Grenêche for SFEN (France)
Plenary Speakers:
• Mr. Christophe Behar, Nuclear Energy Director, CEA (France)
• Ms. Tracy Mustin, Principal Deputy Assistant Secretary for EM,
DOE (USA)
• Mr. Francois-Michel Gonnot, Chairman of the Board, Andra
(France)
— BREAK —
• Dr. Tero Varjoranta, Director, Division of Nuclear Fuel Cycle and
Waste Technology, IAEA (Austria)
• Mr. Arnaud Gay, Executive Vice President of the Nuclear Sites
Value Development Business Unit, AREVA (France)
• Conference Organization and Administration: Gary Benda,
ICEM Conference Manager (USA)
SESSION 2
Monday: 1:45pm - 6:00pm Room: 1
PANEL: APPROACHES FOR INTERNATIONAL
COLLABORATION (5.18)
Co-Chairs: Rosa Ramirez, US DOE (USA)
John Mathieson, UK Nuclear Decommissioning
Authority (UK)
Organizers: Ana Han, US DOE
An important element to reducing the cost and schedule of a country’s
and/or organization’s environmental remediation mission is
forming key international collaborative partnerships that focus on
identifying and leveraging international expertise, infrastructure, and
collaboration opportunities. This panel will provide an overview of
the different approaches and initiatives used to promote international
collaboration in environmental remediation and/or radioactive waste
management, with a focus on the challenges and opportunities unique
to each country and/or organization.
Panelists include: Mark Butez, Andra (France); John Mathieson,
NDA (UK); Ian Bainbridge, AECL (Canada); Jong-Kil Park,
KHNP (Korea); Malgorzata K. Sneve, Norwegian Radiation Protection
Authority (Norway)
SESSION 3
Monday: 1:45pm - 6:00pm Room: Salle Royale
PANEL: LESSONS LEARNED: FUKUSHIMA, CHERNOBYL-
25 YEARS LATER, TMI-2 & OTHER EXPERIENCES (3.11)
Co-Chairs: Jas S. Devgun, Sargent & Lundy (USA)
Jean-Guy Nokhamzon, CEA/DEN/DADN
(France)
Organizers: Jas S. Devgun and Jean-Guy Nokhamzon
This panel was initially planned to discuss confinement activities and
lessons learned from Chernobyl at a time of 25th anniversary of the
Chernobyl accident (April 26, 1986), lessons from TMI-2 accident
(March 28, 1979) and other industry experience with smaller events.
However, the natural events of March 11, 2011 (large earthquake and
18
tsunami) led to the accident at the Fukushima- Dai-ichi complex
which has been given the highest rating of seven on the international
scale, equivalent to that of the 1986 Chernobyl crisis. The recovery
efforts at Fukushima are still ongoing. This panel will discuss lessons
learned from Fukushima, Chernobyl, and TMI-2 related to recovery,
confinement, decommissioning, and future design lessons.
Panelists include: Dr. Tero Varjoranta, IAEA (Austria); Sergii
Mitichkin, Chernobyl NPP (Ukraine); Thomas Chauveau,
Bouygues-Construction (France); Didier Dall’ava,
CEA/DEN/DADN (France); Svetlana Bratskaya, Institute of Chemistry
of Russian Academy of Science (Russia); and Dominique
Greneche, SFEN (France)
SESSION 4
Monday: 1:45pm - 6:00pm Room: 2
NATIONAL AND INTERNATIONAL PROGRAMS FOR L/ILW
MANAGEMENT (1.2)
Co-Chairs: Andrew Baker, Eden Nuclear and Environment
Ltd. (UK)
Michel Dutzer, Andra (France)
Organizers/Reviewers: Keith Anderson and David Wallace
1. Low Level Waste Disposal Regulatory Issues in the US
(w/oP-59311)
David James, Thomas Kalinowski, DW James Consulting LLC;
Lisa Edwards, Electric Power Research Inst. (USA)
2. Taking the UK’s National LLW Progamme from Strategy
Development to Implementation (w/oP-59059)
David Rossiter, Rachel O’Donnell, LLW Repository Ltd. (UK)
3. CEA’s Waste Management Policy and Strategy. Lessons
Learned (w/oP-ICEM2011-59201)
Didier Dall’ava, CEA (France)
4. Regulations for the Disposal of Radioactive Waste in the
Konrad Repository (w/oP-ICEM2011-59105)
Hagen Gunther Jung, Lower Saxony Water Management,
Coastal Protection and Nature Conservation Agency (NLWKN);
Gabriele Bandt, TÜV Nord EnSys Hannover GmbH & Co. KG
(Germany)
— BREAK —
5. The Hydrogeologic Environment for a Proposed Deep
Geologic Repository in Canada for Low and Intermediate
Level Radioactive Waste (w/oP-59285)
Jonathan Sykes, Stefano Normani, Yong Yin, University of
Waterloo; Mark Jensen, Nuclear Waste Management
Organization (Canada)
6. Radioactive Waste Management Challenges and Progress in
Iraq (wP-59164)
Fouad Al-Musawi, Emad Shamsaldin, Ministry of Science &
Technology (Iraq); John Cochran, Sandia National Laboratories
(USA)
SESSON 5
Monday: 1:45pm - 6:00pm Room: 3
L/ILW TREATMENT TECHNOLOGY DEVELOPMENT AND
IMPLEMENTATION (1.15)
Co-Chairs: Hans Codee, COVRA N.V. (Netherlands)
Keith Anderson, ECC (USA)
Organizers/Reviewers: Hans Codee and Keith Anderson
1. Research and Technology Delivery at Sellafield, UK (w/oP-
59372)
Mike James, Sellafield Ltd (UK)
2. Waste Loading Enhancements for Hanford LAW Glasses
(wP-59018)
Albert Kruger, US Department of Energy WTP Engineering
Division (USA)
3. THOR(R) Steam Reforming Technology for the Treatment
of Complex and Problematic Wastes (wP-59084)
J. Brad Mason, Adam L. Foster, Studsvik, Inc.(USA)

Technical Sessions Monday PM
4. A Room Temperature Stabilization and Waste Volume
Reduction Method Tested on Belgian Intermediate-Level
Homogeneous Bituminized Waste (Eurobitum) (wP-59103)
Nathalie R.E.N. Impens, SCK-CEN; Jan Deckers,
BelgoProcess; Lesley Adriaensen, Pierre Van Iseghem,
Studiecentrum voor Kernenergie-Centre d’Etude de l’Energie
Nucléaire (Belgium) — BREAK —
5. Standardizing of LLW/ILW Treatment for Russian Type
Pressure Water Reactors (w/oP-59233)
Klaus Buettner, Rainer Slametschka, NUKEM Technologies
GmbH (Germany)
6. 35 Years of Incineration in Studsvik, Lessons Learned and
Recent Modifications and Improvements (wP-59264)
Maria Lindberg, Karin von Kronhelm, Joakim Lövstrand,
Studsvik Nuclear AB (Sweden)
7. Sodium-Rich Wastes: Challenges, Analysis and Performance
(w/oP-59316)
Daniel Brew, Melody L Carter, Lou Vance, Martin W Stewart,
ANSTO (Australia)
8. Preliminary Demonstration of GeoMelt Treatment of
Hanford’s K-Basin Sludge (wP-59004)
Keith Witwer, IMPACT Services, Inc. (USA)
SESSION 6
Monday: 1:45pm - 6:00pm Room: 4
ISSUES AND SOLUTIONS RELATED TO SPENT FUEL, TRU,
AND HLW TRANSPORTATION AND DISPOSAL (2-5)
Co-Chairs: Mike Garamszeghy, Nuclear Waste Management
Organization (Canada)
Jean Paul Chiles, Ecole Mines (France)
Organizers/Reviewers: Jeffrey Griffin and Jean Paul Chiles
1. Initial Assessment of Radon in a Deep Geological Repository
for Used Nuclear Fuel (wP-59145)
Kelly Sedor, Frank Garisto, Helen Leung, Nuclear Waste
Management Organization (Canada)
2. Groundwater Flow Modeling of Periods with Temperate
Climate Conditions for use in a Safety Assessment of a
Repository for Spent Nuclear Fuel (w/oP-59154)
Steven Joyce, Lee Hartley, Serco; Trevor Simpson, Serco (UK)
3. Conception of a New Conditioning Process, of Strongly
Plutonium Contaminated Waste Canisters (w/oP-59205)
Maxime Michel-Noel, ONET Technologies-ONECTRA (France)
4. Methodological Guide on Development of Work Plan for
Mitigation of Accident Consequences during Transportation
of Radioisotope Thermoelectric Generators and
Radioisotope Heat Sources (w/oP-59162)
Valeriy Shempelev, Scientific and Engineering Centre for
Nuclear and Radiation Safety; Vladimir Reka, Rostechnadzor;
Malgorzata Sneve, Norwegian Radiation Protection Authority;
Alexander Smetnik, Evgenij Kapralov, FSUE VO “Safety”;
Galina Zubareva, Tver State Medical Academy (Russia/Norway)
— BREAK —
5. Physical and Chemical Processes during Vacuum Drying of
Metallic Spent Nuclear Fuel (wP-59114)
Martin Plys, Michael Epstein, Sung Jin Lee, Robert Apthorpe,
Fauske & Associates LLC (USA)
6. Security Issues for Long-Term Storage of Used Fuel
(w/oP-59380)
Felicia A Durán, Gregory Wyss, Calvin Jaeger, Sandia National
Laboratories (USA)
SESSION 7
Monday: 1:45pm-6:00pm Room: 5
NATIONAL AND INTERNATIONAL ER PROGRAMS (4.2)
Co-Chairs: Leo P.M. Velzen, Nuclear Research and
Consultancy Group (Netherlands)
Nick DiMascio, Bartlett Services Inc. (USA)
Organizers/Reviewers: Steve Brown and Leo Van Velzen
1. Objectives for Remediation of Areas Polluted by Radioactive
Substances in France (w/oP-59300)
Charlotte Cazala, Didier Gay, Olivier Chabanis, Jerome
Guillevic, IRSN; Odile Palut Laurent, Geraldine Dandrieux,
ASN; Alain Thomassin, IRSN/DRPH/SER/UETP; Chapalain
Estelle, Laurence Roy, Ministère de lEcologie, du
Développement Durable, des Transports et du Logement
(France)
2. Remediation of AREVA Miramas Site (w/oP-59312)
Gilles Potier, AREVA (France)
3. The Value of a Mature, Stable, and Transparent Regulatory
Framework in Facilitating ER Programs Lessons Learned in
Decommissioning of Uranium Recovery and Other Facilities
in the USA (w/oP-59411)
Keith I. McConnell, Larry Camper, U.S. Nuclear Regulatory
Commission (USA)
4. The First New Conventional Uranium Mill in the U.S. in 30
Years Licensing of the Pinon Ridge Project, Colorado, USA
(w/oP-59330)
Steve Brown, SENES Consultants Ltd; Frank Filas, Energy
Fuels Resources, Lakewood, (USA)
— BREAK —
5. Integrated Program Management for Major Nuclear
Decommissioning and Environmental Remediation Projects
(w/oP-59068)
John Lehew, CH2M Hill Plateau Remediation Company (USA)
6. EPRI Nuclear Power Plant Groundwater Protection
Program (w/oP-59341)
Karen Kim, Electric Power Research Institute (USA) -
Presentation by Sean Bushart, EPRI (USA)
7. Clean Up Strategies and Results in USIN Site in São Paulo
City, Brazil (w/oP-59243)
Rodrigo Raposo de Almeida, Federal Fluminense University;
Valter J.G. Mortágua, Industrias Nucleares do Brasil (Brazil)
8. Application of an Environmental Remediation Methodology:
Theory vs. Practice. Reflections and Two Belgian Case
Studies (wP-59184)
Koen Mannaerts, Stephane Pepin, Boris Dehandschutter, Walter
Blommaert, Federal Agency for Nuclear Control (FANC)
(Belgium)
SESSION 8
Monday: 1:45pm - 6:00pm Room: 10
EXPERIENCES IN ER CLEAN-UP METHODS AND ACTIONS
(4.4)
Co-Chairs: Dawn Kaback, AMEC (USA)
Virgene Mulligan, ARS International, Inc. (USA)
Organizers: Didier Dubot and Steve Brown
Reviewers: Susan Walter and Walter Van Hecke
1. Groundwater Remediation of Hexavalent Chromium along
the Columbia River at the Hanford Site in Washington State,
USA (wP-59030)
Dyan Foss, CH2M Hill Plateau Remediation Company; Briant
Charboneau, DOE RL (USA)
2. Environmental Remediation of an Alstom Grid Industrial
Site (France) (wP-59270)
Stéphanie Romero, ALSTOM GRID (France)
3. Design and Installation of a Permeable Treatment Wall to
Passively Remove Strontium-90 from Groundwater at a
Former Commercial Nuclear Fuel Reprocessing Facility in
New York (wP-59292)
Douglas Bablitch, Rupeet Malhotra, Richard Frappa, Scott
Warner, AMEC Geomatrix (USA)
19

Monday PM Technical Sessions
4. Decommissioning of the Active Storage Facility for Residuals
in Rheinsberg (Brandenburg/Germany) and Results of
Groundwater Monitoring (wP-59134)
Mathias Steinhoff, Öko-Institut e.V. (Germany)
— BREAK —
5. Environmental Surveillance System for the Shchuchye Site
(wP-59042)
Stephane Belbeze, Matthieu Hallouin, Antea (France)
6. 25 Years After Chernobyl NPP Accident: Experience and
Trends of Radioactive Contaminated Soils Rehabilitation in
Belarus (wP-59242)
Leanid Maskalchuk, JIPNR-Sosny NAS of Belarus (Belarus)
SESSION 9
Monday: 12:30pm - 6:00pm Room: Exhibit Hall
POSTER SESSION: LOW/INTERMEDIATE LEVEL WASTE
MANAGEMENT (1.1)
Co-Chairs: Steve Rima, AMEC (USA)
Cathy Hickey, CH2M Hill (USA)
Reviewers: Donald Goebel, Vickie Maranville, and David Wallace
1. Numerical Modeling for Colloid-Facilitated Migration of N-
Number Radionuclides Chains in the Fractured Rock (w/oP-
59257)
Chun-Ping Jen, National Chung Cheng University (Taiwan)
2. Laboratory Experiments on the Alteration of Highly-
Compacted Bentonite by Alkaline Solution and the Effects
on Physical Properties (wP-59318)
Satoru Miyoshi, Shinya Morikami, Yukinobu Kimura, Tomoko
Jinno, Shuichi Yamamoto, Obayashi Corporation (Japan)
3. Gas Transport Properties of Pumice Tuff for Performance
Assessment of LLW Disposal Facility (wP-59074)
Shuichi Yamamoto, Kenichiro Suzuki, Obayashi Corporation;
Mamoru Kumagai, Japan Nuclear Fuel Limited; Yasuhiro
Tawara, Koji Mori, Geosphere Environmental Technology
Corporation (Japan)
4. Extraction and Confinement of Caesium Using
Functionalized Porous Materials (w/oP-59106)
Carole Delchet, Guillaume Toquer, Agnès Grandjean, Institut de
Chimie Séparative de Marcoule; Joulia Larionova, Yannick
GUARI (France)
5. Photocatalytic and Photochemistry Degradation of Liquid
Waste Containing EDTA (wP-59144)
Célia Lepeytre, Cyril Lavaud, Guillaume Serve, CEA Marcoule
(France)
6. Historical Waste – Biological Shield & Documentation
during Decommissioning (w/oP-59056)
Thomas Nellemann, Anne Sørensen, Danish Decommissioning
(Denmark)
7. A Numerical Interpretation of Density Homogenization of
Bentonite Material in Wetting Process (wP-59153)
Atsushi Iizuka, Yusuke Takayama, Katsuyuki Kawai, Kobe
University; Shinya Tachibana, Saitama University; Shintaro
Ohno, Ichizo Kobayashi, Kajima Corporation (Japan)
8. Comparison of Organic and Inorganic Ion Exchangers for
the Treatment of Radioactive Liquid Wastes by Ion
Exchange Processes (w/oP-59107)
Yves Barre, CEA (France)
9. Detritiation of JET Plasma Facing Components (w/oP-
59345)
Pierre Trabuc, Karine Liger, Nicolas Ghirelli, Christophe
Perrais, CEA (France)
10. Experimental Drop Testing of Waste Containers for the
KONRAD Repository (w/oP-59269)
Tino Neumeyer, Karsten Müller, Holger Voelzke, Federal
Institute for Materials Research and Testing (BAM) (Germany)
11. Instrumented Measurements on Radioactive Waste Disposal
Containers during Experimental Drop Testing (wP-59142)
Thomas Quercetti, Andre Musolff, Karsten Müller, BAM -
Federal Institute for Materials Research and Testing (Germany)
20
12. Regulatory Clearance of Spent Steel Drums (wP-59405)
Dae-Seok Hong, Korea Atomic Energy Research Institute;
Young-Yong Ji, Il-Sik Kang, Kyoung-Kil Kwak, Woo-Seog Ryu,
KAERI (Korea)
13. Liquid Waste Treatment Process (w/oP-59061)
Bouchta Moussaif, Touria Lambarki el Allioui, CNESTEN
(Morocco)
14. Cast Iron Transport, Storage and Disposal Containers for
use in UK Nuclear Licensed Sites (w/oP-59412)
Joerg Viermann, Matthias P Messer, GNS Gesellschaft fuer
Nuklear-Service mbH (UK)
15. Optimization of Radioactive Waste Cementation for
Decommissioning of Salaspils Research Reactor (wP-59066)
Gunta Abramenkova, Maris Klavins, University of Latvia;
Andris Abramenkovs, Latvian Environment, Geology and
Meteorology Centre (Latvia)
16. Bayesian Statistics Applied to the Activities of Waste Drums
(wP-59081)
Richard Bull, Ian Adsley, Nuvia Limited (UK)
17. Physical Modelling of Turbulent Jets for Nuclear Sludge
Mobilisation (wP-59147)
Donna McKendrick, Institute of Particle Science and
Engineering; Simon Biggs, Michael Fairweather, James Young,
University of Leeds (UK)
18. Environmentally-Friendly Recovery of Uranium from
Nuclear Fuel Scraps Generated at Nuclear Fuel Fabrication
Process (wP-59383)
Kwang-Wook Kim, Dong-Yong Chung, Eil-Hee Lee, Keun-
Young Lee, Kune Woo Lee, Jei-Kwon Moon, Korea Atomic
Energy Research Insititute (Korea)
19. Self Cleaning HEPA Filtration Without Interrupting Process
Flow (wP-59347)
Chris Chadwick, Porvair Filtration Group (UK)
20. Steam and Condensate Tolerant HEPA Filter - Substitute for
ESP (wP-59346)
Chris Chadwick, Porvair Filtration Group (UK)
21. Status of Site Investigation for L/ILW Facilities in the
Philippines (wP-59262)
Maria V. Palattao, Carl Nohay, Rolando Reyes, Alfonso
Singayan, Philippine Nuclear Research Institute (Philippines);
Dirk Mallants, Belgian Nuclear Research Centre SCK-CEN
(Belgium)
22. Management of Smoke Detectors Containing Radioactive
Sources (wP-59049)
Mercedes Salgado Mojena, Juan Carlos Benitez Navarro, Juan
Miguel Hernandez García, Rafael Castillo Gomez, Ania
Berdellans Escobar, CPHR (Cuba); Carlos Jose Pirez, Pedro
Graciano Soto, Atomic Centre Ezeiza, National Commission of
Atomic Energy (Argentina)
23. Curing Time effect on the Fraction of 137 CS from
Immobilized Radioactive Evaporator Sludge by Cement
(wP-59006)
Ilija Plecas, Slavko Dimovic, Vinca Institute of Nuclear
Sciences; Radojica Pesic, Nuclear Facilities of Serbia (Serbia)
24. An Approach for the Development of a Comprehensive Data
Base of Time-Dependent Hydraulic and Transport
Parameters for Concrete Engineered Barriers (wP-59299)
Suresh Seetharam, Dirk Mallants, Janez Perko, Diederik
Jacques, SCK.CEN (Belgium)
25. Radiation Protection Experiences in Retrieval of Radioactive
Waste at Püspökszilágy Repository (wP-59054)
László Juhász, National Research Institute for Radiobiology
and Radiohygiene; Sándor Kapitány, István Barnabás, Public
Limited Company for Radioactive Waste Management; Anna
Mária Motoc, National Research Institute for Radiobiology and
Radiohygiene (Hungary)

Technical Sessions Tuesday AM
SESSION 10
Tuesday: 8:30am - 12:30pm Room: 1
PANEL: EMERGING ISSUES IN THE MANAGEMENT OF
I/ILW (1.16)
Co-Chairs: Michel Dutzer, Andra (France)
Angie Jones, AMEC (USA)
Organizer: Michel Dutzer
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. There will be discussion on large, disused
components that are part of the decommissioning L/ILW waste
stream. The engineering of facilities for the disposal of all such wastes
should be proportionate to the long-term environmental impact that
might arise.
Panelists include: Irena Mele, Section Head of Waste Technology,
IAEA (Austria); Keith McConnell, Deputy Director, US NRC (USA);
Bruno Cahen, Director, Andra (France); Geraldine Dandrieux,
Head of Waste, Research Facilities and Fuel Cycle Facilities
Department (France); Kazuyuki Kato, Federation of Electric Power
Companies (Japan); Paul Dixon, Los Alamos National Lab (USA);
and Dick Raaz, Chairman and Director, UK LLWR (UK)
SESSION 11
Tuesday: 8:30am-12:30pm Room: 4
PANEL: HOW CAN NETWORKS IMPROVE THE
IMPLEMENTATION OF ER PROJECTS? THE IAEA
NETWORK ON ENVIRONMENTAL MANAGEMENT AND
REMEDIATION-ENVIRONET (4.15)
Co-Chairs: Leo Van Velzen, EURSSEM, NRG (Netherlands)
Rosa Ramirez, US DOE (USA)
Organizer: Horst Monken Fernandes
Environmental remediation projects tend to be constrained by several
aspects being the lack of financial resources one of the most
prominent factors. However, even when financial resources are
available lack of institutional framework (e.g. lack of regulations),
lack of human resources, and absence of a solid technical basis at the
national level will contribute to slow the pace of implementation.
Networking intends to bring problem holders and solution donors
together and enhance the exchange of experience while fostering the
construction of partnerships. The ENVIRONET was initially
presented to the international community at WM 2010. The ICEM
2011 will be an opportunity to present its achievement, broaden its
affiliation and build an agenda of activities for the next years.
Panelists include: Leo van Velzen, NRD (Netherlands); Peter
Booth, WSP Group (UK); and joining after the break - Irena Mele,
Section Head of Waste Technology, IAEA (Austria)
SESSION 12
Tuesday: 8:30am - 12:30pm Room: 2
WASTE MINIMIZATION, AVOIDANCE, AND RECYCLING
(1.3)
Co-Chairs: Ian Beadle, AMEC (UK)
Kapila Fernando, ANSTO (Australia)
Organizers/Reviewers: Ian Beadle and Kapila Fernando
1. Waste Minimization by Melting - Recycling of Radioactive
Metals (wP-59040)
Thomas Kluth, Ulrich Quade, Siempelkamp Nukleartechnik
GmbH (Germany)
2. Waste Minimization Benefits of Dissolvable Protective
Clothing (wP-59003)
Michael Cournoyer, David Wannigman, Robert Dodge, Los
Alamos National Laboratory (USA)
3. Evaluation of External Exposure during Building and
Operation of Concrete Bridges Constructions that Reuse the
Conditionally Released Steels (wP-59120)
Michal Panik, Vladimir Necas, Slovak University of Technology
(Slovakia)
4. Treatment of Spent Acidic Decontaminants with a High-
Efficiency Cementation Method (wP-59063)
Kou-Ming Lin, Ching-Tu Chang, Ming-Shin Wu, Wen-Chen
Lee, Jen-Chieh Chung, Tsong-Yang Wei, Institute of Nuclear
Energy Research (Taiwan)
— BREAK —
5. Methodology for Identification of Conditionally Released
Materials from Decommissioning using the OMEGA Code
(wP-59175)
Matej Zachar, Vladimír Daniaka, DECOM, a.s.; Vladimir
Necas, Slovak University of Technology (Slovakia)
6. Impact of Nuclide Vector Composition Contained in
Conditionally Released Steel Reused In Motorway Tunnels
Scenario on Calculated Individual Effective Doses (wP-
59128)
Tomas Hrncir, Vladimir Necas, Slovak University of Technology
(Slovakia)
7. Evaluation of Technical, Economic and Financial Feasibility
for Recycling and Reprocessing of Radioactive Waste from a
Remediation Work of Low and Medium Activity for the
Extraction of Heavy Minerals (w/oP-59231)
Rodrigo Raposo de Almeida, Federal Fluminense University;
Valter J.G. Mortágua, Industrias Nucleares do Brasil (Brazil)
8. WNA Statement - Towards Greater Efficiency in the
Management of Low-Level Radioactive Material that
Concurrently Supports Reuse, Recycling and Disposal (w/p -
59414)
Sylvain Saint-Pierre, World Nuclear Association (WNA) (UK)
SESSION 13
Tuesday: 8:30am - 12:30pm Room: 3
HLW, FISSILE, TRU AND SPENT FUEL SHORT AND LONG-
TERM STORAGE ISSUES (2.4)
Co-Chairs: Vince Dilworth, ASME (USA)
Organizer: James Blankenhorn, Permafix Environmental
Services Inc. (USA)
Reviewer: Bill Wilmarth
1. West Valley Demonstration Project High Level, Transuranic,
and Greater than Class C Wastes (wP-59048)
James Blankenhorn, West Valley Environmental Services (USA)
2. Managing Aging Effects on Used Fuel Dry Cask for Very
Long-Term Storage (wP-59067)
Omesh Chopra, Dwight Diercks, David Ma, Vik Shah, Shiu-
Wing Tam, Ralph Fabian, Yung Liu, Mark Nutt, Argonne
National Laboratory (ANL)(USA)
3. Application of Coupled Thermo-Hydro-Mechanical-
Chemical (THMC) Process In Hydrothermal Systems To
Process Near A High-Level Nuclear Waste Repository (wP-
59246)
Geoffrey Peter, Oregon Institute of Technology Portland Center
(USA)
4. Generic Design Assessment of Long-Term Spent Fuel
Storage for New Reactors in the UK (wP-59174)
Christopher Fisher, Nuclear Directorate, Health and Safety
Executive; Dave Watson, Office of Nuclear Regulation; Ian
Streatfield, Colette Grundy, Saffron Price-Walter, Environment
Agency, Dave Glazbrook, Office of Nuclear Regulation (UK)
— BREAK —
6. Industrial Complementarities between Interim Storage and
Reversible Geological Repository (wP-59237)
Jean-Michel Hoorelbeke, Andra (France)
7. Recent Developments in Spent Fuel Management in Norway
(wP-59260)
Peter Bennett, Barbara Oberlander, Erlend Larsen, Institutt for
Energiteknikk (Norway
21

Tuesday AM Technical Sessions
8. Advanced Surveillance Technologies for Used Fuel Long-
Term Storage and Transportation (wP-59032)
Hanchung Tsai, Yung Liu, Mark Nutt, Argonne National
Laboratory; James Shuler, US Department of Energy (USA)
SESSION 14
Tuesday: 8:30am - 12:30am Room: 5
D&D OF POWER REACTORS AND RESEARCH REACTORS
(3.9)
Co-Chairs: Jean-Marie Cuchet, BELGONUCLEAIRE (Belgium)
Kenneth Kok, ASME (USA)
Organizers: Jean-Marie Cuchet and Jas S. Devgun
1. DfD an Approach to New Reactor Designs (wP-59197)
Jas S. Devgun, Sargent & Lundy (USA)
2. Feedback from Westinghouse Experience on Segmentation
of Reactor Vessel Internals (wP-59013)
Joseph Boucau, Westinghouse Electric Company; Stefan
Fallström, Westinghouse; Per Segerud, Westinghouse Electric
Sweden; Paul Kreitman, Westinghouse Electric Company
(Belgium/Sweden/USA)
3. Update on Jose Cabrera NPP Decommissioning (wP-59322)
Juan Santiago, Nieves Martin, Manuel Rodriguez, ENRESA
(Spain)
4. The Decommissioning of the CIEMAT Nuclear Research
Centre (w/oP-59321)
Juan Santiago, Sergio Vidaechea, Manuel Ondaro, ENRESA
(Spain)
— BREAK —
5. The Removal, Transportation and Final Treatment and
Conditioning of the Thetis Research Reactor Spent Fuel of
the University of Ghent (Belgium) Achieved in 2010 Authors
(wP-59261)
Hubert Thierens, Myriam Monsieurs, Ghent University; Vincent
De pooter, Marnix Braeckeveldt, NIRAS/ONDRAF; Luc
Noynaert, SCK●CEN; Patrick Lewandowski, Belgoprocess;
Patrick Maris, Luc Ooms, SCK●CEN; Karel Strijckmans, Ghent
University (Belgium)
6. Decommissioning and Dismantling of the French Brennilis
NPP (w/oP-59366)
Thierry Andre, ONET Technologies; Werner Botzem, Nukem
Technologies (France/Germany)
7. The Chooz a Reactor Dismantling Project (wP-59363)
Estelle Grevin, EDF; Joseph Boucau, Westinghouse Electric
Company (France/Belgium)
8. Full System Decontamination (FSD) Prior to Decommissioning
(wP-59189)
Christoph Stiepani, AREVA NP GmbH (Germany)
SESSION 15
Tuesday: 8:30am - 10:15am Room: 10
THE FRENCH D&D ACTIVITIES - ORGANIZATION,
STRATEGY, OBJECTIVES AND EXPERIENCE (3.2)
Co-Chairs: Jean-Guy Nokhamzon, CEA/DEN/DADN (France)
Jim Marra, US DOE (USA)
Organizer: Jean-Guy Nokhamzon
Reviewers: Jean-Guy Nokhamzon and Andy Szilagyi
1. CEA’s Decommissioning Policy and Strategies. Lessons
Learned (w/oP-59203)
Philippe Guiberteau, Didier Dall’ava, CEA; Jean-Guy
Nokhamzon, CEA/DEN/DADN (France)
2. Cleansing and Dismantling of CEA-Saclay Nuclear Licensed
Facilities (w/oP -59227)
Michel K. Jeanjacques, Rebecca Glévarec, Isabelle Delaire,
Jean Louis Martin, Commissariat à l’Energie Atomique et aux
Energies Alternatives (France)
3. Decontamination and Dismantling of CENDRILLON
Transfer Systems for Radioactive Liquid Solutions (w/oP -
59336)
Michel K. Jeanjacques, Commissariat à l’Energie Atomique et
aux Energies Alternatives; Frédéric Masure, Alternative
Energies and Atomic Energy Commission (France)
22
4. AREVA Return on Experience from D&D Programme
Management - What we have Learned so Far? (w/oP -59324)
Jean-Michel Chabeuf, Thierry Varet, Grégoire de Laval, Guy
Decobert, Frédéric Chambon, AREVA Nuclear Site Value
Development BU (France)
SESSION 16
Tuesday: 10:45am - 12:30pm Room: 10
NATIONAL AND INTERNATIONAL D&D PROGRAMS (3.3)
Co-Chairs: Sean Bushart, Electric Power Research Institute (USA)
Thibaud Labalette, Andra (France)
Organizers: Jas Devgun and Thierry Varet
Reviewers: Sean Bushart and Dominique Greneche
1. Particularities of CHNPP Site Remediation During its
Decommissioning (wP-59193)
Sergii Mitichkin, Valeriy Seyda, Chernobyl NPP (Ukraine)
2. Division of Nuclear Liabilities between different License
Holders and Owners (wP-59214)
Staffan Lindskog, Swedísh Radiation Safety Authority; Rolf
Sjöblom, Tekedo AB (Sweden)
3. Spanish Approach to Large Decommissioning Projects (wP-
59320)
Juan Santiago, Alejandro Rodríguez, ENRESA (Spain)
4. Decommissioning of Obsolete Nuclear Facilities in the
Nuclear Research Institute Rez (wP-59309)
Josef Podlaha, Karel Svoboda, Nuclear Research Institute Rez;
Eduard Hanslik, T.G.M. Water Research Institute (Czech
Republic)
SESSION 17
Tuesday: 8:30am - 10:15am Room: 6
APPLYING STRATEGIC PLANNING, DECISION-MAKING
AND RISK REDUCTION METHODOLOGIES IN EM (5.7)
Co-Chairs: Mark Nutt, ANL (USA)
Dominique Francois-Bongarcon,
AGORATEK International Consultants (Canada)
Organizer: Roger Seitz
Reviewers: Roger Seitz and Dominique Francois-Bongarcon
1. Can Sustainability be Applied to our Environmental
Remediation Challenges? (w/oP-59148)
Peter Booth, Vicky Gaskin, WSP Environment and Energy (UK)
2. Evolution of Performance Assessment Modeling in the US
(w/oP- 59334)
Paul Black, John Tauxe, Neptune and Company, Inc. (USA)
SESSION 18
Tuesday: 10:45am - 12:30pm Room: 6
ECONOMIC ANALYSES, MONITORING STRATEGIES AND
PROJECT MANAGEMENT IN ENVIRONMENTAL
MANAGEMENT (5.6)
Co-Chairs: Yvette Collazo, US DOE (USA)
Paul Black, Neptune and Company, Inc. (USA)
Organizers: Judy Connell and Yvette Collazo
Reviewers: Yvette Collazo and Paul Black
1. Delivering Value for Money - Trust and Verify? (wP-59253)
Alastair Laird, Project Time & Cost Inc. (USA)
2. The Technical and Economical Optimization of the French
Geological Repository Project (w/oP-59275)
Rodolphe Raffard, Thibaud Labalette, Andra (France)
3. The Environmental Monitoring System Developed within
the Framework of the French Radioactive Waste Deep
Repository Project (w/oP-59296)
Elisabeth Leclerc; Patrick Landais, Andra (France)

Technical Sessions Tuesday PM
SESSION 19
Tuesday: 12:00pm-6:00pm Room: Exhibit Hall
POSTER SESSION: SPENT FUEL, FISSILE, TRANSURANIC
AND HIGH LEVEL WASTE MANAGEMENT (2.1)
Co-Chairs: Ed Bentz, E.J. Bentz & Associates (USA)
Heather Klebba, NFT (USA)
Reviewers: Heather Klebba, Gerald Ouzounian, and Ed Bentz
1. ADONIS, High Count Rate Hp-Ge ƴ Spectrometry
Algorithm: Irradiated Fuel Assembly Measurement
(wP-59234)
Patrick Pin, AREVA NC; Eric Barat, Thomas Dautremer,
Thierry Montagu, Stéphane Normand, CEA - Saclay (France)
2. Technical Know-How for the Investigation and Modelling of
Topographic Evolution for Site Characterisation
(wP-59171)
Ryosuke Doke, Ken-ichi Yasue, Tadafumi Niizato, Akio
Nakayasu, Japan Atomic Energy Agency (Japan)
3. Validation of Correlations between ND Isotopes and
Difficult-To-Measure Nuclides Predicted with Burn-Up
Calculation Code By Post Irradiation Examination
(wP-59086)
Shiho Asai, Keisuke Okumura, Yukiko Hanzawa, Hideya Suzuki,
Masaaki Toshimitsu, Jun Inagawa, Takaumi Kimura, Japan
Atomic Energy Agency; Satoru Kaneko, Kensuke Suzuki, Tokyo
Electric Power Company (Japan)
4. Computational Study for Inventory Estimation of Se-79, Tc-
99, Sn-126, and Cs-135 in High-Level Radioactive Wastes
from Spent Nuclear Fuels of Light Water Reactors
(wP-59087)
Keisuke Okumura, Shiho Asai, Yukiko Hanzawa, Tsutomu
Okamoto, Hideya Suzuki, Masaaki Toshimitsu, Jun Inagawa,
Takaumi Kimura, Japan Atomic Energy Agency; Satoru Kaneko,
Kensuke Suzuki, Tokyo Electric Power Company (Japan)
5. Industrial Scale HL-LL Waste Canister Transfer
Demonstrator (wP-59305)
Pascal Champ, Jacques Bardet, Benjamin Attias, Cegelec
(France)
6. CESAR5.3: An Industrial Tool for Irradiated Nuclear Fuel
and Waste Characterisation, with an Associated
Qualification (w/oP-59080)
Jean-Marc Vidal, Romain Eschbach, Commissariat à lÉnergie
Atomique et aux Énergies Alternatives; Agnes Launay,
Christophe Binet, AREVA_NC (France)
7. Test Procedure with a 15,000 kg half-scale Prototype of
Transport and Storage Cask (w/oP-59141)
Andre Musolff, Thomas Quercetti, Karsten Müller, BAM -
Federal Institute for Materials Research and Testing (Germany)
8. Capillary Electrophoresis with Laser-Induced Fluorescent
Detection Method Using Highly Emissive Probes for Analysis
of Actinides in Radioactive Wastes (wP-59092)
Tomoko Haraga, Japan Atomic Energy Agency; Yuta Nakano,
Masami Shibukawa, Saitama University; Yutaka Kameo,
Kuniaki Takahashi, Japan Atomic Energy Agency; Shingo Saito,
Saitama University (Japan)
9. A New Way of Eliminating Tributylphosphate and Dodecane
Mixtures Using Advanced Oxidation Techniques
(w/oP-59104)
Geraldine Dupuy, DEWDROPS (France)
10. The FP7 Collaborative Project ReCosy (w/oP-59397)
Gunnar Buckau, Institute for Transuranium Elements, Joint
Research Center, European Union; Anne Delos, Vanessa
Montoya, Amphos 21 (Germany/France/Spain)
11. Technical Know-How of Site Descriptive Modeling for Site
Characterization (wP-59089)
Hiromitsu Saegusa, Tadafumi Niizato, Ken-ichi Yasue, Hironori
Onoe, Ryosuke Doke, Japan Atomic Energy Agency (Japan)
12. A Comprehensive Information Management System for
European Disposal R&D (INMAN): A Proposal for the Next
European Framework Program (w/oP-59397)
Gunnar Buckau, Institute for Transuranium Elements, Joint
Research Center, European Union; Anne Delos,Vanessa
Montoya, Amphos 21 (Germany/France/Spain)
13. Development of Comprehensive Techniques for Coastal Site
Characterization: Integrated Palaeohydrogeological
Approach for Development of Site Evolution Models
(wP-59259)
Kenji Amano, Tadafumi Niizato, Kunio Ota, Japan Atomic
Energy Agency; Bill Lanyon, Nagra; W Russell Alexander,
Bedrock Geosciences (Japan/Switzerland)
SESSION 20
Tuesday: 1:45pm - 6:00pm Room: 1
PANEL: CHALLENGES WHEN SELECTING DISPOSAL
OPTIONS IN THE LIGHT OF THE NEW IAEA
CLASSIFICATION SCHEME (1.17)
Co-Chairs: Angie Jones, AMEC (USA)
Peter Ormai, IAEA (Austria)
Organizer: Peter Ormai
The new IAEA classification scheme is based on long term safety –
primarily disposal. The potential options for disposal include: above
surface engineered landfill, near surface disposal (trenches, vaults or
shallow boreholes), engineered facilities at intermediate depth (10s to
100s of meters) and geological disposal (> few hundred metres).
Specific waste types will need specific consideration (e.g. disused
sealed sources, graphite waste, and radium bearing waste). National
schemes will be circumstance dependent.
The following will be discussed:
• Near surface or geological disposal for SL-LILW
• Separate disposal for SL-LILW and VLLW
• Advantages and disadvantages of opting for co-disposal
• Borehole disposal as potential solution for the countries having
limited waste inventories
• Feasible approaches for disposal of low level long-lived waste
This panel will provide a forum for the exchange of scientific and
technical information on disposal of different categories of radioactive
waste with focus on current approaches.
Panelists include: Linde Nel, Director of Operations and
Maintenance Services (South Africa); Vaclav Hanusik, Senior
Researcher, VUJE (Slovak Republic); Dr. Irina Gaus, Senior Expert
(Switzerland); Thibaud Labalette, Program Director at Andra
(France); Balint Nos, Head of Strategy Development and
Engineering Office of PURAM (Hungary); Dr. Peter Brennecke,
Bundestamt fur Strahlenschutz (BFS), Retired (Germany); Dr.
Kazumi Kitayama, Senior Technical Advisor, Nuclear Waste
Management Organization of Japan (NUMO) (Japan); and Keith
McConnell, Deputy Director, US NRC (USA)
SESSION 21
Tuesday: 1:45pm-3:30pm Room: 4
PANEL: CONTRIBUTION AND COMPLEMENTARITIES OF
INTERIM STORAGE, GEOLOGICAL DISPOSAL,
PARTITIONING & TRANSMUTATION REVERSIBILITY
REGARDING GLOBAL OPTIMIZATION OF RADWASTE
MANAGEMENT (2.15)
Co-Chairs: Jean-Michel Hoorelbeke, Andra (France)
Heather Klebba, NFT (USA)
Organizer: Jean-Michel Hoorelbeke
Session 21 is a two part panel in conjunction with Session 22. The
first part will consist of a introductory paper and then a panel will
address the status of HLW and Spent Fuel interim storage, processing
and national programs. Partitioning and transmutation are also
investigated in several countries. Interim storage is required to
accommodate waste as long as sustainable management solutions are
not available and interim storage duration up to 100 years has been
often considered.
Panelists include: Bernard Boullis, CEA (France); Wilhelm
Bollingerfehr, DBE (Germany); Philippe Lallieux ONDRAF
(Belgium); Claudio Pescatore, NEA, (France); Jean-Michel
Hoorelbeke, Andra (France); Farok Sharif, URS (USA); Jürg
Schneider, NAGRA (Switzerland); and Neil Smart, NDA (UK)
23

Tuesday PM Technical Sessions
1. New Nuclear Programmes Must Not Neglect Waste
Management (wP-59077)
Charles McCombie, Arius Association (Switzerland)
SESSION 22
Tuesday: 4:15pm-6:00pm Room: 4
PANEL: CONTRIBUTION AND COMPLEMENTARITIES OF
INTERIM STORAGE, GEOLOGICAL DISPOSAL,
PARTITIONING & TRANSMUTATION REVERSIBILITY
REGARDING GLOBAL OPTIMIZATION OF RADWASTE
MANAGEMENT (2.15)
Co-Chairs: Jean-Michel Hoorelbeke, Andra (France)
Heather Klebba, NFT (USA)
Organizer: Jean-Michel Hoorelbeke
Session 22, the second part of this two part panel will discuss final
disposition and geological disposal issues since it is internationally
recognized as the reference option for long term management of high
level and TRU waste, or non reprocessed spent fuel. Nevertheless the
progress of geological repositories varies significantly from one
country to another. In many cases some reversibility or irretrievability
is expected by stakeholders.
Specialists know that geological repository will not suppress the need
for interim storage, and that partitioning and transmutation cannot
suppress the need for geological disposal. The panel will discuss the
potential complementarities of these various waste management tools,
or their incompatibilities if any, with regard to possible optimization
of the whole system. Different time scales and types of waste will be
considered as necessary.
Panelists include: Bernard Boullis, CEA (France); Wilhelm
Bollingerfehr, DBE (Germany); Philippe Lallieux ONDRAF
(Belgium); Claudio Pescatore, NEA, France; Jean-Michel
Hoorelbeke, Andra (France); Farok Sharif, URS (USA); Jürg
Schneider, NAGRA (Switzerland); and Neil Smart, NDA (UK)
SESSION 23
Tuesday: 1:45pm-3:30pm Room: 2
ADVANCED L/ILW CONDITIONING TECHNOLOGIES -
PART 1 OF 2 (1.11)
Co-Chairs: Mike Garamszeghy, Nuclear Waste Management
Organization (Canada)
Andrew Baker, Eden Nuclear and Environment
Ltd. (UK)
Organizer: Angie Jones
Reviewers: Mike Garamszeghy and Andrew Baker
1. Cementitious Materials for Radioactive Waste Management
Within IAEA Coordinated Research Project (wP-59021)
Zoran Drace, IAEA; Michael Ojovan, University of Sheffield
(Austria/UK)
2. Elution Behavior of Heavy Metals from Cement Solidified
Products of Incinerated Ash Waste (wP-59102)
Yoshihiro Meguro, Yoshimi Kawato, Takuya Nakayama,Osamu
Tomioka, Motoyuki Mitsuda, Japan Atomic Energy Agency
(Japan)
3. Immobilisation of Radwaste in Synthetic Rock: An
Alternative to Cementation (W/P-59008)
Bernard Rottner, Onet Technologies (France)
24
SESSION 24
Tuesday: 4:15-6:00pm Room: 2
L/ILW WASTE CHARACTERIZATION, ASSAY, AND
TRACKING SYSTEMS - PART 1 OF 2 (1.7)
Co-Chairs: Jeffrey Lively, AMEC (USA)
Jerome Brueziere, AREVA (France)
Organizers: Ronald Keyser and Karan North
Reviewers: Karan North and Jerome Brueziere
1. A Proposed Figure of Merit for Evaluating the Performance
of Radiation Identification and Detection Systems
(wP-59159)
Ronald Keyser, Timothy Twomey, ORTEC - AMETEK; Michael
D. Belbot, Thermo Fisher Scientific; Neil Andrew Webster,
Thermo Fisher Scientific, Radiation Measurement & Security
Instruments (USA)
2. Characterization of Legacy Low Level Waste at the SVAFO
Facility Using Gamma Non-Destructive Assay and X-Ray
Non-Destructive Examination Techniques (wP-59289)
Stephen Halliwell, VJ Technologies Inc; Gary Mottershead, VJ
Technologies Inc; Fredrik Ekenborg (USA/France/Sweden)
3. Calibration and Validation of a Wide Range Segmented
Gamma Ray Scanning Instruments for the Measurement of
Low and Intermediate Level Waste (wP-59304)
John Mason, A. N. Technology Ltd.; Kapila Fernando, ANSTO,
Australia Nuclear Science and Technology Organization
(UK/Australia)
4. Performance of a DrumScan® HRGS Solo Scanner for the
Assay of Legacy Waste at the Belgoprocess Site (wP-59122)
Daniel Parvin, Babcock International Group; Thomas Huys,
Belgoprocess, Dessel, (UK/Belgium)
SESSION 25
Tuesday: 1:45-6:00pm Room: 3
D&D OF NON-REACTOR NUCLEAR FACILITIES (3.10)
Co-Chairs: Kenneth Kok, ASME (USA)
Lucien Pillette-Cousin, Areva (France)
Organizers: Jas Devgun and Jean-Guy Nokhamcon
Reviewers: Ken Kok and Lucien Pillette-Cousin
1. Decommissioning The Belgonucleaire Dessel Mox Plant:
Presentation of The Project And Situation on 30/06/2011
(wP-59027)
Jean-Marie Cuchet, Carlo Verheyen, Henri Libon,
Belgonucleaire; Jos Custers, Tecnubel; Robert Walthery,
Belgoprocess; Jozef Bily, Studsvik (Germany)
2. Uranium Workshops Dismantling and Criticality Control
(wP-59060)
Pierre Lisbonne, Julie Rosello, CEA (France)
3. The Complex Challenge of Refurbishing the Pond Gantry
Steelwork which Supports the Pond Skip Handler above the
First Generation Magnox Storage Pond at Sellafield (wP-
59133)
Ian Richardson, Sellafield (UK)
4. Systematic Chemical Decontamination Using IF7 Gas
(wP-59036)
Haruhi Hata, Kaoru Yokoyama, Noritake Sugitsue, Japan
Atomic Energy Agency (Japan)
— BREAK —
5. Decommissioning & Demolition of Facilities used for the
Storage & Stabilisation of Water Reactor Sludge (wP-59097)
Nicholas J. Brown, Rowland Cornell, Nuvia Limited; Andy
Staples, RSRL (UK)
6. Decommissioning of the Radio Chemical Hot Laboratory of
the European Commission Joint Research Centre of ISPRA
(wP-59207)
Daniele Ugolini, Francesco Rossi, Francesco Basile, European
Commission Joint Research Centre (Italy)
7. A Successful Transition from Operating to Dismantling a
UO2-PuO2 Fuel Fabrication Facility (w/oP-59326)
Thierry Flament, AREVA NC (France)

Technical Sessions Tuesday PM
SESSION 26
Tuesday: 1:45pm-6:00pm Room: 5
D&D TECHNOLOGIES - PART 1 OF 2 (3.4)
Co-Chairs: Jas Devgun, Sargent & Lundy (USA)
Jean-Guy Nokhamzon, CEA/DEN/DADN
(France)
Organizer/Reviewer: Jas Devgun
1. Dismantling/Remediation of a Highly Contaminated Sump
in Running Plant Conditions (w/oP-59053)
Jos Boussu, Koen Lenie, Tecnubel (Belgium)
2. New Degreasing Formulations for the Decontamination of
Solid Substrates, Consistent with Vitrification Process of the
Final Wastes (w/oP-59166)
Jeremy Causse, Cyril Roussignol, French Atomic Enrgy
Commission; Jean-François Valery, Jean Charles Hamel, Areva
NC (France)
3. The Orion ScanSort Soil Sorting System (w/oP-59385)
Jeffrey Lively, MACTEC (USA)
4. Liquids, Gels, Foams and Supercritical Fluids: Four States
of Matter for Radioactive Decontamination of Solids
(w/oP-59158)
Sylvain Faure, Jérémy Causse, Bruno Fournel, CEA (France)
— BREAK —
5. Decommissioning of the A-1 NPP Heavy Water Evaporator
Facility (wP-59225)
Jan Medved, VUJE Inc.; Ladislav Vargovcik, ZTS VVU Kosice
a.s. (Slovakia)
6. Remote Decommissioning of Blind Cells - APM 214 Facility
CEA Marcoule (w/oP-59206)
Olivier Calixte, ONET Technologies - ONECTRA (France)
7. Transport of Nuclear Waste Flows - A Modeling and
Simulation Approach (wP-59136)
Jonathan Adams, Michael Fairweather, James Young, Simon
Biggs, Jun Yao, University of Leeds, Leeds (UK)
8. Fuel Racks Dismantling Workshop at CENTRACO Facility
(wP-59365)
Jean-François Rives, Christophe Maufrais, SOCODEI (France)
SESSION 27
Tuesday: 1:45pm-6:00pm Room: 10
ER SITE CHARACTERIZATION AND MONITORING - PART
1 OF 2 (4.5)
Co-Chairs: Nicolas Jeannée, GEOVARIANCES (France)
Virgene Mulligan, ARS International, Inc. (USA)
Organizers: Steve Brown and Didier Dubot
Reviewers: Nicolas Jeannée and Virgene Mulligan
1. Soils Radiological Characterization Under a Nuclear Facility
(wP-59046)
Emilie Aubonnet, Geovariances / CEA FAR, Fontenay aux
Roses, France, Didier Dubot, CEA/FAR/USLT/SPRE/SAS,
Fontenay aux Roses (France)
2. Radiological Evaluation of Contaminated Sites and Soils
VEGAS: An Expertise and Investigating Vehicle (wP-59057)
Julien Attiogbe, GEOVARIANCES; Marie Lavielle, Patrick De
Moura, CEA (France)
3. Determination of the Radionuclide Contamination on the
Absheron Peninsula in Azerbaijan (wP-59177)
Tjalle Vandergraaf, Providence University College; Gudrat G
Mamedov, Mahammadali A. Ramazanov, Baku State University;
Jalal A. Naghiyev, Institute of Radiation Problems; Afat A.
Mehdiyeva, National Aerospace Agency of Azerbaijan; Nazim A.
Huseynov, Institute of Radiation Problems (Canada/Azerbaijan)
4. High-density Gamma Radiation Spectrometry Surveys of
Contaminated Land (wP-59076)
Mike Davies, Robert Clark, Ian Adsley, Nuvia Limited (UK)
— BREAK —
5. Remediation and Assessment of the National Radioactive
Waste Storage and Disposal Site in Tajikistan (wP-59110)
Nazirzhon Buriev, Dzhamshed Abdushukurov, Physical-
Technical Institute of the Academy of Sciences of the Republic of
Tajikistan; Tjalle Vandergraaf, Providence University College
(Tajikistan/Canada)
6. Integrating History and Measurement into a Case for Site
Release (wP-59131)
Angela Bartlett, Research Sites Restoration Limited; Mike
Davies, Pete Burgess, Nuvia Ltd; Gavin Coppins, Babcock
International Group (UK)
7. Characterization of a Deep Radiological Contamination:
Integration of Geostatistical Processing and Historical Data
(wP-59062)
Yvon Desnoyers, GEOVARIANCES; Patrick De Moura, CEA
(France)
8. Industrial Experience Feedback of a Geostatistical
Estimation of Contaminated Soil Volumes (wP-59181)
Claire Faucheux, Nicolas Jeannée, GEOVARIANCES(France)
SESSION 28
Tuesday: 1:45pm - 6:00pm Room: 6
PUBLIC PERCEPTION ISSUES AND STAKEHOLDER
ENGAGEMENT STRATEGIES IN RADIOACTIVE
ENVIRONMENTAL MANAGEMENT (5.5)
Co-Chairs: Judy Connell, Fluor Government Group (USA)
Sebastien Farin, Andra (France)
Organizer: Judy Connell
Reviewers: Judy Connell and Sebastien Farin
1. Perspectives on Reversibility and Retrievability of a
Geological Repository in France (wP - 59263)
Jean-Noel Dumont, Jean-Michel Hoorelbeke, Andra (France)
2. A Dialogue-Centric Approach to Environmental
Remediation Decision-Making (wP -59115)
Laurel Boucher, The Laurel Co.; James Clark, CRX Group, Inc.
(USA)
3. Outreach and Education - Ensuring a Clean Energy Future
for All (wP - 59339)
Susan Hess, Areva Inc USA)
4. Challenge in the Public Acceptance and Cooperation in the
Verge of Building the First Nuclear Power Plant in Indonesia
(wP - 59119)
Putero Susetyo Hario, Santosa Haryono Budi, Gadjah Mada
University (Indonesia)
— BREAK —
5. Andra Long Term Memory Project (wP - 59277)
Patrick Charton, Fabrice Boissier, Guillaume Martin, Andra
(France)
6. Engaging Local Stakeholders on Technical Issues: Test Case
at the La Hague Reprocessing Plant (wP - 59211)
Ludivine Gilli, Institut de radioprotection et de sûreténucléaire
(IRSN) (France)
7. Creating and Managing Radioactive Waste Disposal
Facilities with the Involvement of the Local Populations
(w/oP - 59286)
Sébastien Farin, Andra (France)
SESSION 29
Wednesday: 8:30am-12:30pm Room: 1
PANEL: INTERNATIONAL COOPERATION: NEA ROAD
MAP, HOW TO INCREASE SYNERGY (3.12)
Co-Chairs: Hans Riotte, OECD/NEA (France)
Jean-Guy Nokhamzon, CEA/DEN/DADN
(France)
Organizers: Hans Riotte and Jean-Guy Nokhamzon
This session will start with short presentations and conclude with a
panel session. The presentations will include;
1. Recent Work And Achievements At The Nuclear Energy
Agency InDecommissioning: Claudio Pescatore (OECD/NEA)
25

Wednesday AM Technical Sessions
2. Cooperative Program on Dismantling and Decommissioning
(CPD) -Overview, Jan Carlson & Jean-Guy Nokhamzon
3. CPD - Decontamination and Dismantling of Concrete
Structures, Eric Cantrel (CEN/SCK/Mol)
4. CPD -Experience with Remote Handling Techniques, Pierre
Valentin (CEA/DEN/DPAD)
5. Working Party on Dismantling and Decommissioning
(WPDD) - Overview, Ivo Tripputi (Sogin)
— BREAK —
6. WPDD -Integration of Waste Management and
Decommissioning: The Management of Large Components,
Michel Dutzer (Andra)
7. WPDD -Decommissioning Techniques: Prospects for R &D,
Gerard Laurent (EDF/CIDEN)
8. WPDD -Decommissioning Costs: Yellow book and Cost
Control, Patrick Devaux (CEA/DEN/DPAD)
9. WPDD -Decommissioning Feedback for New Nuclear Power
Plants, Rateb Abu-Eid (US/NRC)
The session will end with a panel discussions moderated by Ivo
Tripputi (Sogin).
Panelists include: Juan Luis Santiago (Enresa), Jim Marra (US
DOE), and Gerard Laurent (EDF/CIDEN)
SESSION 30
Wednesday: 8:30am - 12:30pm Room: 2
SITING, DESIGN, CONSTRUCTION, AND OPERATION OF
L/ILW DISPOSAL FACILITIES - PART 1 OF 2 (1.12)
Co-Chairs: Philip Rendell, NDA (UK)
Patrice Torres, Andra (France)
Organizers/Reviewers: Cathy Hickey and Philip Rendell
1. An Innovative Design for Low and Intermediate Radwaste
Near Surface Repository in Lithuania (w/oP-59382)
Boniface Jean-Michel, AREVA TA (France)
2. Product Quality Control of Radioactive Waste with a Special
Regard to Federal States Collecting Facilities (w/oP-59176)
Markus Havertz, Research Centre Jülich GmbH (Germany)
3. Centre de la Manche: A Disposal Facility in Institutional
Control (wP-59236)
Michel Dutzer, Jean Pierre Vervialle, Alain André, Albert
Marchiol, Andra (France)
4. Radiological Impact of Co-Location of the VLLW and LILW
Repository at Mochovce site (wP-59152)
Václav Hanusík, Zdena Kusovská, Jozef Morávek, VUJE, Inc.;
J. Balaz, O. Chren, Nuclear and Decommissioning Company
plc. (Slovakia)
— BREAK —
5. Development of an Engineering Design Process and
Associated Systems and Procedures for a UK Geological
Disposal Facility (wP-59160)
Philip Rendell, NDA; Henry O’Grady, Parsons Brinckerhoff:
Brendan Breen, Alastair Clark, Steve Reece, NDA (UK)
6. State of the Art for Fabricating and Emplacing Concrete
Containers into Large Horizontal Disposal Caverns in the
French Geological Repository (wP-59267)
Jean-Michel Bosgiraud, Maurice Guariso, François Pineau,
Andra (France)
7. On-Site, Near Surface Disposal of Graphite Wastes in the
UK (wP-59078)
Adam Meehan, Peter Sibley, EnergySolutions; Jeremy
Lightfoot, Golder Associates (UK) Ltd.; Duncan Jackson, Eden
Nuclear & Environment Ltd., (UK)
26
SESSION 31
Wednesday: 8:30am - 12:30pm Room: 3
L/ILW WASTE CHARACTERIZATION, ASSAY, AND
TRACKING SYSTEMS - PART 2 OF 2 (1.18)
Co-Chairs: Ronald Keyser, ORTEC - AMETEK (USA)
Jerome Brueziere, AREVA (France)
Organizers: Ronald Keyser and Karan North
Reviewers: Ronald Keyser and Jerome Brueziere
1. Non-Destructive Examination of TRU Waste in Low and
High Density Boxes and Drums, using High Energy Real
Time Radioscopy (HE-RTR) and Wide Dynamic Range
Imaging (wP-59302)
Stephen Halliwell, VJ Technologies Inc. (USA)
2. Measurement Methodology for Fulfilling of Waste
Acceptance Criteria for Low and Intermediate Level
Radioactive Waste in Storages (wP-59016)
Marina Sokcic-Kostic, Felix Langer, Roland Schultheis,
NUKEM Technologies GmbH (Germany)
3. Disposition of Transuranic Residues from Plutonium
Isentropic Compression Experiment (Pu-ICE) conducted at
Z Machine (LA-UR-10-05649) (wP-59186)
Kapil K. Goyal, Los Alamos National Laboratory; Betty J.
Humphrey, Weston Solutions Inc.; Jeffry Gluth, Ktech
Corporation/Sandia National Laboratory; David M. French,
Los Alamos National Laboratory (USA)
4. Detection of Shielded Sealed Radioactive Sources in
Radioactive Waste by Non-Destructive Assay Techniques
(wP-59252)
Leo P.M. Velzen, Nuclear Research and Consultancy Group;
Steven van der Marck, Nuclear Research Group (Netherlands)
— BREAK —
5. Use of Lanthanum Bromide Detectors to Augment Site
Surveys for Depleted Uranium (w/P-59169)
Charles Waggoner, Mississippi State University; Ronald Unz,
Institute for Clean Energy Technology; Donna Rogers,
Mississippi State University; Charles R. Jones, Jay P. McCown,
Institute for Clean Energy Technology/Mississippi State
University (USA)
6. Ultrasonic Techniques for the In Situ Characterisation of
‘Legacy’ Waste Sludges & Dispersions (wP-59111)
Timothy Hunter, Jeff Peakall, Simon Biggs, Michael
Fairweather, James Young, University of Leeds, Leeds (UK)
7. Free-Release and Sorting Monitors Developed for NPP A-1
Decommissioning, Slovakia (wP-59071)
Ondrej Slávik, VUJE; Alojz Slaninka, VUJE, a.s./ Slovak
University of Technology in Bratislava; Martin Liatjak, Kamil
Kravárik, VUJE, a.s.; Igor Pély, JAVYS, a.s. (Slovakia)
8. Design and Operation of the Combined Technology
Automated Waste Characterisation System (wP- 59308)
John Mason, Marc R Looman, Robert A. Price, A. N.
Technology Ltd. (UK)
SESSION 32
Wednesday: 8:30am - 12:30pm Room: 4
REPOSITORY PROGRAMS: SITE SELECTION &
CHARACTERIZATION, UNDERGROUND RESEARCH LABS,
ENGINEERING & GEOLOGICAL BARRIERS - PART 1 OF 2
(2.3)
Co-Chairs: Irina Gaus, Nagra (Switzerland)
Jean Paul Chiles, Ecole Mines (France)
Organizers: Irina Gaus and Johan Andersson
Reviewers: Irina Guas and Jean-Paul Chiles
1. Safety Assessment Input to Site Selection - The Swedish
Example (wP-59031)
Johan Andersson, JA Streamflow AB (Sweden)
2. Technical Know-How of Selection Process for the Horonobe
Underground Research Laboratory Area and Site
(wP-59088)
Takanori Kunimaru, Ryuji Takeuchi, Tatsuji Matsuzaki, Japan
Atomic Energy Agency (Japan)

Technical Sessions Wednesday AM
3. Characterisation of Bedrock Hydrogeology at the Olkiluoto
Site Using Surface Based and Underground Data
(w/oP-59095)
Lee Hartley, Dave Swan, Steven Baxter, SERCO (UK)
4. Self-Disposal Option for Heat-Generating Waste (wP-59182)
Michael Ojovan, University of Sheffield; Pavel Poluektov,
Vladimir Kascheev, A.A. Bochvar’s VNIINM (UK/Russia)
— BREAK —
5. NUMOs Approach for Long-term Safety Assessment
(wP-59404)
Takeshi Ebashi, Kenichi Kaku, Katsuhiko Ishiguro, Nuclear
Waste Management Organization of Japan (NUMO) (Japan)
6. Modeling Approaches for Evaluating the Effect of
Heterogeneity on Two-Phase Flow Associated with the
Migration of Waste-Generated Gas from SF/HLW- and
L/ILW Repositories in Low-Permeability Formations (wP-
59196)
Alexandros Papafotiou, Rainer Senger, Intera Inc. Swiss
Branch; Andrés Alcolea, TK Consult AG; William Lanyon,
Fracture-Systems Ltd; John Ewing, Intera Inc. Swiss Branch
(Switzerland/UK)
7. A New Safety Concept for Geological Disposal in Japan (II)
(wP-59357)
Kazumi Kitayama, Nuclear Waste Management Organization of
Japan (NUMO) (Japan)
8. Thermo-Hydro-Mechanical Simulation of a Heating and
Hydration Experimental Study (China-Mock-Up) in
Unsaturated GMZ Bentonite (wP-59212)
Liang Chen, Ju Wang, Yuemiao Liu, Beijing Research Institute
Of Uranium Geology; Federic Collin, University Of Liège;
Jingli Xie, Beijing Research Institute Of Uranium Geology
(China/Belgium)
SESSION 33
Wednesday: 8:30 - 10:15 Room: 6
RECENT ADVANCES IN PROCESSING AND
IMMBOLIZATION OF HLW, FISSLE MATERIAL AND
TRANSUANIC (TRU) - PART 1 OF 2 (2.14)
Co-Chairs: Mark Denton, Kurion Inc. (USA)
Bernard Vigreux, SFEN (France)
Organizers: Mark Denton and Bill Wilmarth
Reviewers: Mark Denton and Bernard Vigreux
1. Uranium Metal Oxidation, Grinding and Encapsulation in
BoroBond: TRU Waste Management (w/oP-59279)
Kevin Cook, Larry Addington, Beth Utley, Boron Products
(USA)
2. Results of Investigation of High Level Solid Radioactive
Waste from Pits No1 and No2 at the Gremikha Site
(w/oP-59390)
B.S. Stepennov, V.M. Afanasyev, A.Yu. Kazennov, N.V. Kartashev,
A.V. Korolev, O.E. Kiknadze, D.V. Pavlov, Kurchatov Institute;
V.V. Eremenko, FGUP SevRAO; G. Fady, CEA; Lucien Pillette-
Cousin, Areva TA (Russia/France)
3. Pilot Test of Precipitation Setup for Dust Supressor and
Transuranic Elements Removal from Wastewaters of
Chernobyl Nuclear Power Plant (w/oP-59256)
Valentin Avramenko, Svetlana Bratskaya, Dmitry Marinin,
Institute of Chemistry FEBRAS; Anatoliy Terzi, Mariya
Yarmolyuk, Chernobyl Nuclear Power Plant (Russia/Ukraine)
4. Separation Processes for the Pretreatment of High-Level
Nuclear Wastes at the Savannah River Site (w/oP-59291)
David Hobbs, Aiken, Thomas Peters, Kathryn Taylor-Pashow,
Fernando Fondeur, Charles Nash, Samuel Fink, David Herman,
Savannah River National Laboratory (SRNL) (USA)
Presentation by: Jim Marra, US DOE (USA)
SESSION 34
(MERGED WITH SESSION 35)
Wednesday: 8:30am - 10:15am Room: 10
URANIUM SITES, ER ISSUES, SITE CHARACTERIZATION
AND MONITORING - PART 2 OF 2 (4.12) (4-6)
Co-Chairs: Stephane Belbeze, Antea Group (France)
Jeroen Welbergen, COVRA (Netherlands)
Organizer: Didier Dubot
Reviewers: Stephane Belbeze and Jeroen Welbergen
1. Sampling in Decommissioning: CETAMA Seminar and
International Overview (w/oP-59209)
Guy Granier, Daniele Roudil, CEA MARCOULE; Didier Dubot,
CEA/FAR/USLT/SPRE/SAS (France)
2. Foam Novel Delivery Technology for Remediation of Vadose
Zone Environments (wP-59019)
Dawn Wellman, Danielle P Jansik, Shas Mattigod, Lirong
Zhong, Pacific Northwest National Laboratory; Yuxin Wu,
Lawrence Berkeley National Lab; Martin Foote, MSE
Technology Applications; Z. F. (Fred) Zhang, Pacific Northwest
National Laboratory; Susan Hubbard, Lawrence Berkeley
National Lab (USA)
3. Mobility of Radium from Pyritic Uranium Mine Tailings
under Sub-aqueous Disposal Conditions (wP-59283)
Nand Dave, Mining and Mineral Sciences Laboratories Canada
(Canada)
4. Remediation Project Planning at the Uranium Production
Legacy Sites. Lesson Learned from the Best International
Practice and Challenges for Developing Countries
(wP-59043)
Oleg Voitsekhovych, Ukrainian Hydrometeorological Institute
(Ukraine)
5. Close-Out of Open Pit and Waste Rock Piles of Daxin
Uranium Mine of China (wP-59073)
Lechang Xu, Changshun Ren, Min Shi, Liaoning Xueli Zhang,
Jie Gao, Beijing Research Institute of Chemical Engineering
and Metallurgy, CNNC (China)
(MERGED WITH SESSION 34)
SESSION 35
SESSION 36
Wednesday: 10:45am - 12:30pm Room: 10
RADIUM REMEDIATION: HISTORICAL PERSPECTIVES
AND CURRENT CIRCUMSTANCES - PART 1 OF 3 (4.11)
Co-Chairs: Robert Zelmer, Atomic Energy of Canada Limited
(Canada)
Steve Brown, SENES Consultants Ltd. (USA)
Organizers/Reviewers: Robert Zelmer & Steve Brown
1. Radium Diagnosis Campaign (wP-59327)
Florence Gabillaud-Poillion, Autorité de Sûreté Nucléaire
(France)
2. Andra’s Remediation Missions (w/oP-59210)
Patrick Poiret, Eric Lanes, Andra (France)
3. Uranium Mill Tailings Remediation in the USA. A History
and Lessons Learned (w/oP-59407)
Steve Rima, AMEC (USA)
4. Remediation of Canada’s Historic Haul Route for Radium
and Uranium Ores: The Northern Transportation Route
(wP-59303)
Robert Brian Geddes, Chris Wenzel, AMEC; Michael Owen,
Mark J. Gardiner, AECL; Julie Brown, Natural Resources
Canada’s (Canada)
27

Wednesday AM Technical Sessions
SESSION 37
Wednesday: 8:30 - 10:15 Room: 5
YOUNG GENERATION NETWORK (YGN) AND
PROFESSIONAL DEVELOPMENT PROGRAMS (5.16)
Co-Chairs: Corhyn Parr, Nuclear Enterprise Ltd (UK)
Connor Deehan, Nukem (UK)
Organizer/Reviewer: Corhyn Parr
1. The Reestablishment of Radiochemistry Academic Programs
in the United States (w/oP-59025)
Craig Williamson, South Carolina Universities Research and
Education Foundation (USA)
2. Planning for Decommissioning of Nuclear Facilities - the
Views of Younger Stakeholders (wP-59222)
Staffan Lindskog, Swedísh Radiation Safety Authority; Bea
Labor, Badania Dydaktycne Project 2010 (Sweden/Poland)
(Final paper received and Copyrights pending)
3. Graduate or Apprentice? How Nuclear Training Provision
has Changed the Shape of the Nuclear Employment Market
(w/oP- 59415)
Corhyn Parr, Nuclear Enterprise (UK)
4. Nuclear Knowledge Development - Overview of the
Activities Proposed by SFEN Young Generation (SFEN-JG)
Guillaume Vaast, SGN–Pierrelatte (France)
SESSION 38
Wednesday: 10:45am - 12:30pm Room: 5
MEETING: YOUNG GENERATION NETWORK (YGN) AND
PROFESSIONAL DEVELOPMENT PROGRAMS (5.17)
Co-Chairs: Corhyn Parr, Nuclear Enterprise Ltd. (UK)
Connor Deehan, Nukem (UK)
Organizers: Corhyn Parr
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 International 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.
For the session we conduct ‘An audience with…….’ where two
leaders of industry provide candid views of their career paths and offer
advice to young professionals answering any questions and providing
advice on career development.
Presenters Include: Sarah Greenwood, AREVA (UK); and Jim
Blankenhorn, Permafix Environmental Services Inc.
SESSION 39A
Wednesday: 8:30am - 5:45pm Room: Exhibit Hall
POSTER SESSION: FACILITY DECONTAMINATION AND
DECOMMISSIONING
Co-Chairs: Keith Anderson, ECC (USA)
Didier Delmont, CEA (France)
Reviewers: Keith Anderson and Didier Delmont
A-1. Use of Highly Presurized Liquid Nitrogen Technology for
Concrete Scabbling Application at SICN Nuclear Facilitiy
(wP-59282)
Fabrice Moggia, Claire-Emilie Vaudey, Thierry Varet, Valérie
Toulemonde, AREVA; Frédéric Richard, Air Liquide CTAS;
Gary Anderson, Nitrocision; Frédérique Damerval, AREVA
(France/USA)
28
A-2. Methodology of External Exposure Calculation for Reuse
of Conditional Released Materials from Decommissioning
(wP-59138)
Frantisek Ondra, Marek Vaako, DECOM, a.s.; Vladimir
Necas, Slovak University of Technology (Slovakia)
A-3. Uncertainty Analysis of Activity Measurement of New
Monitoring System for Free-Release for NPP A-1
Decommissioning, Slovakia (wP-59244)
Alojz Slaninka, VUJE, a.s./ Slovak University of Technology
in Bratislava; Ondrej Slávik, VUJE, a.s.; Vladimir Necas,
Slovak University of Technology (Slovakia)
A-4. Laser Removal of Contaminants on the Metal Surface (wP-
59343)
Hui Jun Won, Jei Kwon Moon, Sun Hee Jung, Chong Hun
Jung, Kune Woo Lee, Korea Atomic Energy Research Institute;
Byung -Sun Choi, Korea Atomic Energy Research Institute
(Korea)
A-5. Influence of the Conditional Release of the Materials with
Very Low Level of Radioactivity on the Environment
(wP -59132)
Slavka Prvakova, University of Economics in Bratislava;
Adela Mrskova, DECOM, A. S.; Jozef Pritrsky, DECOM
(Slovakia)
A-6. Conditional Release of Steel from Decommissioning in a
Form of Reinforced Concrete (wP -59058)
Jozef Pritrsky, DECOM; Miroslav Brodnan, University of
Zilina; Vladimir Necas, Slovak University of Technology
(Slovakia)
A-7. Decommissioning of the UF6 Sphere (w/oP -59200)
Sylvain Chevassu, ONET Technologies - ONECTRA (France)
A-8. Development of Nuclear Facilities Piping Cleaning System
using Microbubble (w/oP-59070)
Jongseon Jeon, SangChul Lee, Byoungsub Han, Enesys Co.,
LTD.; HakSoo Kim, Nuclear Engineering & Technology
Institute; Wisoo Kim, Enesys Co., Ltd. (Korea)
A-9. A Matrix Inversion Method For Gamma-Source Mapping
From Gamma Count Data (wP -59082)
Richard Bull, Claire Burgess, Ian Adsley, Nuvia Limited (UK)
A-10. Decommissioning Activities for Salaspils Research Reactor
(wP -59055)
Andris Abramenkovs, Latvian Environment, Geology and
Meteorology Centre; Jazeps Malnacs, State Environmental
Service (Latvia)
A-11. Technical Justification & Choice for Remediation Methods
(wP -59398)
Mark Morton, Janaka Jayamaha, WorleyParsons (USA)
A-12. New Generation of Diamond Toolings for Facilitating
Decommissioning Operations (wP-59396)
Claude Besson, Erico Mariotti, Alexandre Mouysset, Lorenz
Zur Nedden, Bernard Delannay, Carbodiam (France/Belgium)
A-13. Pompe Secondaire (w/oP -59413)
Anne Durand, CEA (France)
A-14. Tritium Analysis : An Actual Problem for Large Building
Decommissioning (w/oP-59406)
Pascal Fichet, Florence Goutelard, Sylvie Guegan, Aurelie
Robert-Ortis, Nadine Evenat-Robic, Commissariat à l’Energie
Atomique (France)
A-15. Reuse of Conditionally Released Steels; Proposal and
Evaluation of Processes for Manufacturing of Steel
Elements and for Construction of Selected Scenarios (wP-
59130)
Peter Bezák, Eva Hajková, Frantisek Ondra, Vladimír
Daniska, DECOM, a.s.; Vladimir Necas, Slovak University of
Technology (Slovakia)
A-16. The Assessment of the Waste Management Plan to
Decommissioning of Cernavoda NPP for Environmental
Impact Reduction (wP -59358)
Gheorghe Barariu, National Authority for Nuclear Activity -
Subsidiary of Technology and Engineering for Nuclear Project
(Romania)
A-17. Application of the Data Quality Objective Process to the
Partial De-Licensing at Oldbury Nuclear Power Station
(wP -59376)
Denis Buckley, Magnox Ltd, Berkeley (UK)

Technical Sessions Wednesday AM
A-18. Multi-Site Risk-Based Project Planning, Optimization,
Sequencing & Budgeting Process and Tool for the
Integrated Facility Disposition Project (wP -59394)
Jerel Nelson, Carlos Castillo, Julie Huntsman, Heather Lucek,
WorleyParsons; Tim Marks, Omega Consultants (USA)
SESSION 39B
Wednesday: 8:30am - 5:45pm Room: Exhibit Hall
POSTER SESSION: ENVIRONMENTAL REMEDIATION
POSTERS (4.1)
Co-Chairs: Lucien Pillette-Cousin, Areva TA (France)
Michel Dutzer, Andra (France)
Reviewers: Lucien Pillette-Cousin and Michel Dutzer
B-1. Radium Remediation in Canada - History and Present Day
(w/oP-59157)
Mark Gardiner, Michael Owen, Robert Zelmer, AECL
(Canada)
B-2. Mathematical Modeling of Reactive Transport in
Groundwater with Metals and Dissolved Isotopes 226Ra
and 228Ra, USIN, São Paulo, Brazil (w/oP-59245)
Rodrigo Raposo de Almeida, Federal Fluminense University;
Valter Mortágua, Industrias Nucleares do Brasil; Felipe Rosa,
Luciano Magalhaes, Universidade Federal Fluminense
(Brazil)
B-3. Quantifying the Retention of Foam Formulation
Components to Sedimentary Phases to Enable Predictions
of Mobility and Treatment Efficacy (w/oP-59369)
Rosa Ramirez, DOE EM; Danielle Jansik, Dawn Wellman,
Pacific Northwest National Laboratory (USA)
B-4. Techniques of Radioactive Soil Processing at Rehabilitation
of Contamination Territories. (wP-59199)
Victor Volkov, Alexander Chesnokov, Alexey Danilovich, Yury
Zverkov, Sergey Koltyshev, Sergey Semenov, Anatoly Shisha,
RRC Kurchatov Institute (Russia)
B-5. Optimisation (Sampling Strategies and Analytical
Procedures) for Site Specific Environment Monitoring at
the Areas of Uranium Legacy Sites Contamination
Concern in Ukraine (wP-59045)
Oleg Voitsekhovych, Tatiyana Lavrova, Alexander Kostezh,
Ukrainian Hydrometeorological Institute (Ukraine)
SESSION 39C
Wednesday: 8:30am - 5:45pm Room: Exhibit Hall
POSTER SESSION: MAJOR INSTITUTIONAL ISSUES IN
ENVIRONMENTAL MANAGEMENT / PUBLIC
INVOLVEMENT (5.1)
Co-Chairs: Judith Connell, Fluor Government Group (USA)
Gerald Ouzounian, Andra (France)
Reviewers: Judith Connell and Gerald Ouzounian
C-1. Virtual Reality Technology for Radiation Visualisation
during the Remediation at Andreeva Bay in Russia as
Support to Operational and Regulatory Supervision
(wP-59400)
Niels-Kristian Mark, Institute for Energy Technology,
Malgorzata Sneve, Norwegian Radiation Protection Authority
(Norway)
C-2. Taking Risk Asessment and Management to the Next Level
(wP-59395)
Jerel Nelson, Russel Lee Morton, WorleyParsons Polestar;
Carlos Castillo, WorleyParsons; James T. McSwain,
Terragraphics; George Dyer, Natalie Johnson, WorleyParsons;
Gary Nick Kruskall, Link Technologies (USA)
C-3. Radioactive Waste, from Myth to Reality: The Stakes for
Andra’s Educational Communication Efforts (w/oP-59287)
Annabelle Comte, Andra (France)
SESSION 40
Wednesday: 1:45pm - 6:00pm Room: 2
D&D MANAGEMENT APPROACHES AND PLANNING
TOOLS (3.6)
Co-Chairs: Thierry Varet, AREVA (France)
Sean Bushart, EPRI (USA)
Organizers: Jas S. Devgun and Jean-Guy Nokhamzon
Reviewer: Thierry Varet
1. Implementation of the Standardised Listing into
Decommissioning Costing; Examples and Related IAEA
Projects (wP-59313)
Vladimír Daniska, DECOM, a.s.; Michele Laraia, Paul Dinner,
Patrick O’Sullivan, IAEA (Slovikia/Austria)
2. Use of Source Term and Air Dispersion Modeling in
Planning Demolition of Highly Alpha-Contaminated
Buildings (wP-59254)
James G Droppo, Bruce A. Napier, Jeremy P. Rishel, Pacific
Northwest National Laboratory; Richard W. Bloom, CH2M Hill
Plateau Remediation Company (USA)
3. How and Integrated Change Programme has Accelerated
the Reduction in High Risk and High Hazard Nuclear
Facilities at Sellafield (wP-59014)
Angela Mackintosh, Sellafield Ltd. (UK)
4. Use of In-Situ Gamma Spectroscopy During Nuclear Power
Plant Decommissioning (w/oP-59340)
Richard McGrath, Karen Kim, Electric Power Research Institute
(USA) - Presentation by Sean Bushart, EPRI (USA)
— BREAK —
5. Legacy Radioactive Waste Storage - Magnox Swarf Storage
Silo Liquor Effluent Management (wP-59271)
Stephen Le Clere, Sellafield Ltd (UK)
6. Experience of Application of New Remote Controlled
Instruments for Scanning of Distribution of Radioactive
Contamination in Rooms with High Dose Rate (wP-59354)
Vyacheslav Stepanov, Alexey Danilovich, Oleg Ivanov, Victor
Potapov, Sergey Smirnov, Anatoly Volkovich, NRC Kurchatov
Institute (Russia)
7. Human and Organisational Factors as Key Levers of
Performance in D&D Project Management (w/oP-59323)
Thierry Flament, Bertrand Willmann, Grégoire de Laval, Jean-
Louis Lemarch, Alain Cordoba, AREVA (France)
8. Development of Computer Program for Estimating
Decommissioning Cost (wP-59037)
HakSoo Kim, JongKil Park, Nuclear Engineering & Technology
Institute (Korea)
SESSION 41
Wednesday: 1:45pm - 6:00pm Room: 3
D&D TECHNOLOGIES - PART 2 OF 2 (3.13)
Co-Chairs: Jas S. Devgun, Sargent & Lundy (USA)
Bernard Vignau, CEA (France)
Organizer: Jas Devgun
Reviewers: Jas Devgun and Bernard Vignau
1. An Innovative Process for Segmenting of Guide Tubes (wP-
59029)
Patrick (PJ) Gobert, Pierre-Henri Ponchon, Stefan Fallström,
Joseph Boucau, Westinghouse Electric Company
(Belgium/France/Sweden)
2. Assay of Plutonium Contaminated Waste by Gamma
Spectrometry (wP-59039)
Ian Adsley, Michael Green, Ian Pearman, Mike Davies, Nuvia
Limited (UK)
3. Reuse of Conditional Released Materials from
Decommissioning; A Review of Approaches and Scenarios
with Long-Term Constructions (w/oP-59149)
Vladimír Daniska, Jozef Pritrsky, Frantisek Ondra, Ivan Rehák,
Matej Zachar, DECOM, a.s,; Vladimir Necas, Slovak University
of Technology (Slovakia)
29

Wednesday PM Technical Sessions
4. Remediation of a Ventilation Duct Contaminated by Pa-231
(wP-59248)
Pete Burgess, Nuvia Ltd; Clare Irving, Forest Environmental;
Keith Stevens, Nuvia Ltd, (UK)
— BREAK —
5. Measurement of Plutonium Contamination through Paint
Using a Fidler Probe (wP-59250)
Robert Clark, Pete Burgess, Nuvia Ltd; Ian Croudace, GAU-
Radioanalytical Laboratories (UK)
6. The Use of Standard Alpha and Beta Surface Scintillation
Contamination Monitors to Confirm the Contamination
Fingerprint and to Check on Source Quality (wP-59249)
Pete Burgess, Nuvia Ltd (UK)
7. Clearance of Buildings of NPP Würgassen (Germany) Using
an Innovative Clearance Concept (wP-59280)
Stefan Woerlen, Marco Steinbusch, Alexander Kummer, Stefan
Thierfeldt, Frank Schartmann, Brenk Systemplanung (Germany)
8. Characterization of Iraq’s Remote Nuclear Facilities for
Decommissioning and Waste Management (wP-59167)
Fouad Al-Musawi, Adnan S. Jarjies, Ministry of Science and
Technlogy; Ross Miller, Sandia National Laboratories
(Iraq/USA)
SESSION 42
Wednesday: 1:45pm - 6:00pm Room: 5
LIQUID WASTE TREATMENT PROCESS AND EXPERIENCE
(1.8)
Co-Chairs: Michael Ojovan, University of Sheffield (UK)
Andrew Drom, EnergySolutions EU Ltd. (UK)
Organizers/Reviewers: Michael Ojovan and Paul Haigh
1. Nuclide Separation by Hydrothermal Treatment and Ion
Exchange (wP-59217)
Georg Braehler, Ronald Rieck, NUKEM Technologies GmbH;
Valentin Avramenko, Valentin Sergienko, Sergej Shmatko,
Valentin Dobrzhanskyi, Institute of Chemistry FEBRAS; Elmar
Antonov, NTP (Germany/Russia)
2. Decontamination of Strontium from Liquid Radioactive
Wastes by Sodium Nonatitanate (wP-59083)
Merceille Aurélie, CEA Marcoule; Agnès Grandjean, Institut de
Chimie Séparative de Marcoule; Yves Barre, CEA Marcoule
(France)
3. Russia: Results and Prospects of Liquid Solidification
Experiments at ROSATOM Sites (w/oP-59112)
Dennis Kelley, Pacific Nuclear Solutions (USA)
4. Pre-Treatment of Organic Liquid Waste Stream at
Cernavoda NPP (w/oP-59079)
Gabriela Teodorov, Laszlo Toro, Adina Sandru, MATEFIN;
Dennis Kelley, Pacific Nuclear Solutions; Dorin Dumitrescu,
NPP Cernavoda (Romania/ USA)
— BREAK —
5. Transport and Deposition Properties of Model Slurries of
One and Two Particle Species (wP-59140)
Hugh Rice, Simon Biggs, Michael Fairweather, James Young,
University of Leeds, Leeds, (UK)
6. Application of a New Technology For Reprocessing of
Wastes Within the Framework of Rehabilitation of Uranium
Mines Operated by In Situ Leaching (wP-59403)
Gagik Martoyan, Garik Nalbandyan, Lavrenti Gagiyan,
AREV SI CJS Company; Gagik Karamyan, Artak Barseghyan,
Gagik Brutyan, Ecoatom LLC (Armenia)
7. A Fully Operational Pilot Plant for Eliminating Radioactive
Oils Mixed with Chlorinated Solvents (wP-59044)
Albert Jacobs, William Everett, Dewdrops Company (France)
8. Adsorption of Cesium Radionuclides by the Composite
Sorbents Carbon Fiber/Transition Metals Ferrocyanides
(wP-59255)
Irina Sheveleva, Veniamin Zheleznov, Svetlana Bratskaya,
Valeriy Kuryavyi, Valentin Avramenko, Institute of Chemistry
FEBRAS (Russia)
30
SESSION 43
Wednesday: 1:45pm - 3:30pm Room: 6
SITING, DESIGN, CONSTRUCTION, AND OPERATION OF
L/ILW DISPOSAL FACILITIES - PART 2 OF 2 (1.19)
Co-Chairs: Cathy Hickey, CH2M Hill (USA)
Patrice Torres, Andra (France)
Organizers/Reviewers: Cathy Hickey and Philip Rendell
1. 20 Years of Operation for Centre de l’Aube Disposal
Facility: Lessons Learned (w/oP-59235)
Patrice Torres, Laurent Schacherer, Franck Duret, Pascal
Lecoq, Alain Delaplanche, Michel Dutzer, Andra (France)
2. Demonstration Test of Underground Cavern-Type Disposal
Facilities Fiscal 2010 Status (w/oP-59180)
Yoshihiro Akiyama, Kenji Terada, Nobuaki Oda, Tsutomu Yada,
Takahiro Nakajima, Radioactive Waste Management Funding
And Research Center (Japan)
3. Demonstration of Gas Permeable Seals for Radioactive
Waste Repositories Laboratory and In-Situ Experiments
(wP-59224)
Joerg Rueedi, Paul Marschall, Nagra (Switzerland)
4. Post-Iodine Production Norm Repository Technical Design
and Reconstruction Experience in Turkmenistan
(wP-59183)
Alexander Gelbutovsky, Peter Cheremisin, Alexander Troshev,
Alexander Egorov, Mikhail M. Boriskin, Mikhail Bogod,
ECOMET-S (Russia)
SESSION 44
Wednesday: 4:15pm - 6:00pm Room: 6
DISPOSAL SITE AND WASTE FORM CHARACTERIZATION
AND PERFORMANCE ASSESSMENT - PART 1 OF 2 (1.13)
Co-Chairs: Ed Bentz, E.J. Bentz & Associates (USA)
Michel Dutzer, Andra (France)
Organizer: Donald Goebel
Reviewers: Ed Bentz and Michel Dutzer
1. Radiological Characterization of the Dutch Interim Waste
Storage Facility Site (w/oP-59023)
Jeroen Welbergen, COVRA; Leo P.M. Velzen, Nuclear Research
and Consultancy Group (Netherlands)
2. Climate Change Impacts on the Disposal Environment: A
Climate Analogue Approach (wP-59274)
Bertrand Leterme, Dirk Mallants, SCK●CEN (Belgium)
3. Mineralogical Analyses of Old (78 and 98 years) Concrete
(wP-59093)
Tomoko Ishii, Hitoshi Owada, Radioactive Waste Management
Funding and Research Center; Hiroyuki Sakamoto, Masahito
Shibata, Kumi Negishi, Taiheyo Consultant Co.,Ltd. (Japan)
4. Modeling of Alteration Behavior on Blended Cementitious
Materials (wP-59096)
Hitoshi Owada, Tomoko ISHII, Radioactive Waste Management
Funding and Research Center; Mayumi Takazawa, Hiroyasu
Kato, Mitsubishi Materials Corporation; Hiroyuki Sakamoto,
Taiheyo Consultant Co.,Ltd.; Masahito Shibata, Taiheyo
Consultant Co., Ltd. (Japan)

Technical Sessions Wednesday PM
SESSION 45
Wednesday: 1:45pm - 3:30pm Room: 10
REPOSITORY PROGRAMS: SITE SELECTION &
CHARACTERIZATION, UNDERGROUND RESEARCH LABS,
ENGINEERING & GEOLOGICAL BARRIERS - PART 2 OF 2
(2.7)
Co-Chairs: Bill Miller, AMEC (UK)
Johan Andersson, JA Streamflow AB (Sweden)
Organizers/Reviewers: Bill Miller and Johan Andersson
1. EBS Behavior Immediately After Repository Closure in a
Clay Host Rock: The HE-E Experiment (Mont Terri URL)
(wP-59288)
Irina Gaus, Nagra; Klaus Wieczorek, GRS; Juan Carlos Mayor,
ENRESA; Kristof Schuster, BGR; Thomas Trick, Solexperts;
José-Luis Garcia-Siñeriz, Aitemin; Benoit Garitte, CIMNE; Uli
Kuhlman, TK Consult (Switzerland/Germany/Spain)
2. Performance Assessment Modeling for the Geological Siting
Regions for the L/ILW and HLW Repositories in the Context
of the Swiss Site Selection Plan (wP-59306)
Andreas Poller, Juerg Schneider, Piet Zuidema, Nagra;
Johannes Holocher, Gerhard Mayer, AF-Consult Switzerland
Ltd. (Switzerland)
3. Investigations of the Possible Separation Distance between
Spent Fuel/High-Level Waste and a Low/Intermediate-Level
Waste Repositories Due to Gas and Heat Generation
(wP-59220)
Rainer Senger, John Ewing, Intera Inc. Swiss Branch;
(Switzerland)
4. Hydraulic/Mechanical Modeling of Smectitic Materials for
HMC Analytical Evaluation of the Long Term Performance
of TRU Geological Repository (wP-59090)
Ichizo Kobayashi, Kajima Corporation; Hitoshi Owada,
Tomoko Ishill, Radioactive Waste Management Funding and
Research Center (Japan)
SESSION 46
Wednesday: 4:15pm-6:00pm Room: 10
NATIONAL AND INTERNATIONAL PROGRAMS FOR SPENT
FUEL, FISSILE, TRU, AND HLW MANAGEMENT (2.2)
Co-Chairs: Paul Dixon, LANL (USA)
Bernard Vigreux, SFEN (France)
Organizer: Hans Codee
Reviewers: Bernard Vigreux and Hans Codee
1. Implications of Co-existing National and Multinational
Geological Repository Development Programmes in Europe
(wP-59118)
Neil A. Chapman, Charles McCombie, Arius Association;
Ewoud Verhoef, Covra (Switzerland/Netherlands)
2. Regulation of Ageing Facilities - The UK Regulators
Perspective (wP-59353)
Ryan Maitland, Unit 2G Nuclear Installations Inspectorate
(UK)
3. Establishment of Research and Development Priorities
Regarding the Geologic Disposal of Nuclear Waste in the
United States and Strategies for International Collaboration
(wP-59168)
Mark Nutt, Argonne National Laboratory; Michael Voegele,
Complex Systems LLC; Jens Birkholzer, Lawrence Berkeley
National Laboratory; Peter Swift, Sandia National
Laboratories; Jeff Williams, U.S. Department of Energy; Kevin
McMahon, Sandia National Laboratories; Mark Peters,
Argonne National Laboratory (USA)
4. The Cigéo Geological Repository Project (wP-59265)
Thibaud Labalette, Alain Harman, Marie-Claude Dupuis,
Andra (France)
SESSION 47
Wednesday: 1:45pm - 3:30pm Room: 1
RADIUM REMEDIATION HISTORICAL PERSPECTIVES
AND CURRENT CIRCUMSTANCES - PART 2 OF 3 (4.47)
Co-Chairs: Robert Zelmer, Atomic Energy of Canada Limited
(Canada)
Gerald Ouzounian, Andra (France)
Organizers/Reviewers: Robert Zelmer and Gerald Ouzounian
1. Port Radium Start to Finish Life Cycle: A Case Study on
Canada’s Historic Radium/Uranium Mine, Initial Operation
and Closure, Concerns of the Aboriginal Dene People,
Subsequent Assessments, Remediation (wP-59332)
Gerd Wiatzka, SENES Consultants Ltd. (Canada)
Presentation by Steve Brown, SENES Consultants Ltd (USA)
2. Challenges in Developing a Remediation Plan, Procurement
Plan and Long Term Monitoring Program for the Former
Port Radium Uranium Mine that Meets the Needs of the
Community of Deline (w/oP-59333)
Julie Ward, Indian and Northern Affairs Canada (Canada)
3. Overview of Radium Legacies in Belgium (wP-59367)
Stephane Pepin, Koen Mannaerts, Boris Dehandschutter, André
Poffijn, Ludo Jadoul, Walter Blommaert, Michel Sonck, FANC
(Belgium)
4. Preparing for the Construction Phase of The Port Hope Area
Initiative: Canada’s Largest Low-Level Radioactive Waste
Clean-up Project (wP-59307)
Christine Fahey, Andrea Denby, Glenn Case, Atomic Energy of
Canada Ltd.; Tim Palmeter, Public Works Government Services
Canada (Canada)
SESSION 48
Wednesday: 4:15pm - 6:00pm Room: 1
RADIUM REMEDIATION - HISTORICAL PERSPECTIVES
AND CURRENT CIRCUMSTANCES - PART 3 OF 3 (4.13)
Co-Chairs: Robert Zelmer, Atomic Energy of Canada Limited
(Canada)
Gerald Ouzounian, Andra (France)
Organizers: Robert Zelmer and Gerald Ouzounian
An international panel will discuss and compare progress and history
of national radium remediation programs. Lessons learned will be
featured and shared. The outlook for the final closure on this issue
worldwide will also be addressed. The perspectives and panelists
invited include those from practitioners in government policy
leadership, regulatory oversight and licensing, health and safety
impacts and protection, environmental remediation practice and
affected community stakeholders.
Panelists include: Stéphane Pepin, FANC (Belgium); Keith
McConnell, USNRC (USA); Jean-Luc Lachaume, ASN (France); and
Steve Brown, SENES Consultants Ltd. (USA)
SESSION 49
Wednesday: 1:45pm - 3:30pm Room: 4
PANEL: COMMUNICATIONS AND KNOWLEDGE
MANAGEMENT - PART 1 OF 2 (5-21)
Co-Chairs: Jim Marra, US DOE (USA)
Ian Seed, Cogentus Consulting Limited (UK)
Organizer: Jim Marra
This is a two part series of paper presentations and a following panel
session discussion on communications and knowledge management.
Current efforts and views will be presented during this first session.
This session is directly followed by the second part, Panel Session
#50. Presenters will each provide a 10-15 minute overview to the
audience before the break, and will then resume on this topic.
Panelists include: Laurie Judd, NuVision Engineering (USA);
Leonel Lagos, Florida International University (USA); Yanko Yanev,
IAEA (Austria); Hitoshi Makino, JAEA (Japan); Bill Shingler, Fluor
Government Group (USA) and Herve Bienvenu, Andra (France)
31

Wednesday PM Technical Sessions
SESSION 50
Wednesday: 4:15pm - 6:00pm Room: 4
PANEL: COMMUNICATIONS AND KNOWLEDGE
MANAGEMENT - PART 2 OF 2 (5-21)
Co-Chairs: Jim Marra, US DOE (USA)
Ian Seed, Cogentus Consulting Limited (UK)
Organizer: Jim Marra
This panel will provide strategies and lessons learned regarding
general communications and knowledge management to a wide
variety of target audiences, and discuss the earlier presentations.
Communication and management of technical information is a
challenging endeavor. Target groups for technical communications
range from the general public with a cursory knowledge of the subject
matter to highly technical personnel heavily engaged in the work
scope. Communications to the general republic requires deft wording
of technical content and use of attention-grabbing graphics and
illustrations. Managing technical content for highly technical
personnel requires thorough cataloging of subject matter and
providing easy recall and use.
Panelists include: Laurie Judd, NuVision Engineering (USA);
Leonel Lagos, Florida International University (USA); Yanko Yanev,
IAEA (Austria); Hitoshi Makino, JAEA (Japan); Bill Shingler, Fluor
Government Group (USA) and Herve Bienvenu, Andra (France)
SESSION 51
Thursday: 8:30am - 12:30pm Room: 2
SAFETY CONSIDERATIONS ASSOCIATED WITH L/ILW
MANAGEMENT (1.14)
Co-Chairs: Stephen Wickham, Galson Sciences Limited (UK)
Adam Meehan, EnergySolutions/Magnox Ltd. (UK)
Organizers/Reviewers: Stephen Wickham and Ian Crossland
1. UK LLWR Environmental Safety Case Submission 2011
(wP-59135)
Richard Cummings, LLWR Ltd; Andrew Baker, LLWR; Trevor
Sumerling, LLWR; John Shevelan, Amy Huntington, LLWR Ltd.
(UK)
2. An Assessment of the Radiological Impact of Coastal
Erosion of the UK Low-Level Waste Repository (wP-59137)
Trevor Sumerling, LLWR; Paul Fish, Halcrow Ltd.; George
Towler, James Penfold, Quintessa Ltd; John Shevelan, Richard
Cummings, LLWR Ltd. (UK)
3. Development of a Methodology for Determining ILW
Package Monitoring and Inspection Requirements (wP-
59156)
Jenny E. Morris, Timothy W. Hicks, Stephen M. Wickham,
Galson Sciences Limited; Antonio Guida, Babcock International
Group; Melanie Brownridge, James McKinney Darrell Morris,
Nuclear Decommissioning Authority; Mark Tearle, Magnox
Limited (UK)
4. An Assessment of the Radiological Impact of Human
Intrusion at the UK Low Level Waste Repository (LLWR)
(wP-59356)
Timothy Hicks, Tamara Baldwin, Galson Sciences Ltd; Richard
Cummings, LLWR Ltd.; Trevor Sumerling, LLWR (UK)
— BREAK —
5. Factors Affecting the Longevity of Interim ILW Stores,
Monitoring Methods and Techniques Supporting Store Life
Extension (wP-59151)
Jenny E. Morris, Stephen Wickham, Timothy Hicks, Phil J.
Richardson, Galson Sciences Limited; Melanie Brownridge,
Darrell Morris, James McKinney, Nuclear Decommissioning
Authority; Mark Tearle, Magnox Limited (UK)
6. Different Types of Radioactive Waste Repositories, each
Suited for a Given Type of Radioactive Waste (wP-59293)
Sylvie Voinis, Fabrice Boissier, Lise Griffault, Jean Louis
Maillard, Michel Dutzer, Andra (France)
32
SESSION 52
Thursday: 8:30am - 12:30pm Room: 3
DISPOSAL SITE AND WASTE FORM CHARACTERIZATION
AND PERFORMANCE ASSESSMENT - PART 2 OF 2 (1.20)
Co-Chairs: Bill Miller, AMEC (UK)
Patrice Torres, Andra (France)
Organizer/Reviewer: Donald Goebel
1. Characterisation of the Geology of the UK Low Level Waste
Repository (wP-59146)
John Shevelan, LLWR Ltd; Nicholas Smith, National Nuclear
Laboratory (UK)
2. In-Situ Interferometric Measurements of Compacted
Smectite under Hyperalkaline Condition (w/oP-59124)
Hisao Satoh, Susumu Kurosawa, Mitsubishi Materials
Corporation; Tomoko Ishii, Hitoshi Owada, Radioactive Waste
Management Funding and Research Center (Japan)
3. Evolution of Sorption Properties in Large-Scale Concrete
Structures Accounting for Long-Term Physical-Chemical
Concrete Degradation (wP-59297)
Janez Perko, Dirk Mallants, Diederik Jacques, Suresh
Seetharam, SCK●CEN, (Belgium)
— BREAK —
4. Biogeochemical Modelling of the Chemical Evolution of the
Near Field of the UK LLW Repository and effects on
Carbon-14 Release (w/oP-59150)
Joe Small, Christopher Lennon, Liam Abrahamsen, UK
National Nuclear Laboratory; Andrew J. Baker, LLWR (UK)
5. Characterisation and Assessment of the Groundwater
Pathway for the Low Level Waste Repository, UK (wP-
59098)
Lee Hartley, Martin James, Peter Jackson, Matt Couch,
SERCO; John Shevelan, LLWR Ltd (UK)
SESSION 53
Thursday: 8:30am - 10:15am Room: 1
GLOBAL PARTNERSHIPS AND NATIONAL INITIATIVES IN
ENVIRONMENTAL MANAGEMENT - PART 1 OF 2 (5.13)
Co-Chairs: Michael Cull, Teledyne Brown Engineering, Inc.
(USA)
Mark Gerchikov, AMEC NSS (Canada)
Organizers/Reviewers: Michel Cull and Mark Gerchikov
1. Russian Nuclear Submarine Elimination 2001 - 2011 by The
International Community (w/oP-59041)
Michael Washer, Foreign Affairs and International Trade
Canada; Alan Heyes, King’s College (Canada/UK)
2. The Global Partnership: Its Achievements, Missed
Opportunities and Potential to Address Future Threats from
the Spread of CBRN Materials and Expertise (w/oP-59335)
Alan Heyes, Wyn Bowen, Hugh Chalmers, King’s College (UK)
3. The Global Threat Reduction Initiatives Radiological
Security Cooperation with Russia (wP-59361)
Tiffany Blanchard, U.S. Department of Energy/National
Nuclear Security Administration; William Abramson, Lawrence
Livermore National Laboratory; James W. (J.R.) Russell,
National Security Technologies; Catherine Roberts, Pacific
Northwest National Laboratory (USA)
4. Kola Peninsula Radwaste Management in the Framework of
the Italian-Russian Cooperation Agreement for Global
Partnership (wP-59392)
Massimiliano Nobile, SOGIN (Russia)
5. Securing of the Spent Nuclear Fuel Stored on Gremikha Site
- The Former Soviet Submarine Base in North-West of
Russia (w/oP-59371)
Alexandre Gorbatchev, CEA; Lucien Pillette-Cousin, AREVA
TA: Boris Stepennov, NRC KI; Valery Eremenko, SevRAO;
Anatoly Zakharchev, ROSATOM (France/Russia)

Technical Sessions Thursday AM
SESSION 54
Thursday: 10:45am - 12:30pm Room: 1
GLOBAL PARTNERSHIP IN ENVIRONMENTAL
MANAGEMENT - PART 2 OF 2 (5.20)
Co-Chairs: Michael Cull, Teledyne (USA)
Mark Gerchikov, AMEC (Canada)
Organizers/Reviewers: Michael Cull and Mark Gerchikov
1. Environmental and Radiological Remediation Under
Canada’s Global Partnership Program 2004-11 (wP - 59185)
Michael J. Washer, Foreign Affairs and International Trade
Canada (Canada)
2. UK Contributions to the Decommissioning of the BN-350
Reactor in Kazakhstan: 2002 – 2011 (wP-59099)
Steven Laws, Department of Energy and Climate Change (UK),
David Wells and Andrew Herrick, Nuvia Limited (UK)
3. Dismantling of Civilian Nuclear Powered Fleet Technical
Support Vessels. Engineering Solutions. (wP-59386)
Konstantin Kulikov, Rinat Nizamutdinov, NIPTB Onega OAO
(Russia)
4. Progress in International Cooperation on Regulatory of
Legacy Management: Experience in Norwegian Cooperation
Programmes (wP-59399)
Malgorzata Sneve, Norwegian Radiation Protection Authority
(Norway)
5. Methodological and Practical Bases of Providing
Information Support to Activities on Environmental
Remediation of the Spent Nuclear Fuel and Radioactive
Waste Temporary Storage Facility in Gremikha (wP-59375)
Dmitry Stepennov, Anatoly P. Varnavin, NRC Kurchatov
Institute; Anatoly A. Zakharchev, Rosatom; Lucien Pillette-
Cousin, AREVA TA (Russia/France)
SESSION 55
Thursday: 8:30am - 10:15am Room: 4
SAFETY AND SECURITY RELATED TO ENVIRONMENTAL
AND NUCLEAR MATERIALS MANAGEMENT (5.11)
Co-Chairs: Ken Kok, Consultant (USA)
Bernard Vigreux, SFEN (France)
Organizer: Adrian Mendez-Torres
Reviewers: Adrian Mendez-Torres and Philippe Crochon
1. Remote Radiation And Visual Surveys of the Hot Cell Waste
Vault and Spent Fuel Transfer Route at Kazakhstans BN-
350 Reactor (wP-59101)
David Wells, Nuvia Limited, Dorchester,United Kingdom, Collin
Knight, Idaho National Laboratory; Alexander Klepikov,
Nuclear Technology Safety Center; Igor Yakovlev, CRT&TD
MAEC-Kazatomprom LLP; Evgeniy Tur, National Nuclear
Center of the Republic of Kazakhstan; Andrew Herrick, Nuvia
Limited (USA/Kazakhatan/UK)
2. Human Reliability-Based MC&A Modeling for Evaluating
the Effectiveness of Protecting Nuclear Material (wP-59379)
Felicia A Durán, Gregory D. Wyss, Sandia National
Laboratories (USA)
3. Risk-Based Security Cost-Benefit Analysis: Method and
Example Applications (w/oP-59381)
Gregory Wyss, John Hinton, John Clem, Consuelo Silva, Felicia
A Durán, Sandia National Laboratories (USA)
SESSION 56
Thursday: 10:45am - 12:30pm Room: 4
ADVANCED L/ILW TECHNOLOGIES - PART 2 OF 2 (1.21)
Co-Chairs: Ian Beadle, AMEC (UK)
Dominique Greneche, Consultant (France)
Organizer: Angie Jones
Reviewers: Pierre Van Iseghem and Dominique Greneche
1. Applying Fluid Dynamics Simulations to Improve
Processing and Remediation of Nuclear Waste (wP-59172)
Kelly J Knight, Jon M. Berkoe, Brigette M. Rosendall, L. Joel
Peltier, Chris A Kennedy, Bechtel National (USA)
2. Lifetime Performance of ASME AG-1 Section FK Radial
Flow Filters (wP-59170)
Charles Waggoner, Michael Parsons, Paxton Giffen,
Mississippi State University; Jaime Rickert, Institute for Clean
Energy Technology (USA)
3. Alternative Strategies to Reduce Cost and Waste Volume in
HEPA Filtration using Metallic Filter Media (wP-59348)
Chris Chadwick, Porvair Filtration Group (UK)
4. Advanced Drying System to Meet Radiolysis Criteria of
Metallic Waste (wP-59116)
Masamichi Obata, Yasushi Ooishi, Toshiba Corporation
(Japan)
SESSION 57
Thursday: 8:30am - 12:30pm Room: 5
RECENT ADVANCES IN PROCESSING AND
IMMOBILIZATION OF HLW, FISSILE AND TRU -
PART 2 OF 2 (2.6)
Co-Chairs: James Blankenhorn, Permafix Environmental
Services Inc. (USA)
Gerald Ouzounian, Andra (France)
Organizers: Mark Denton and Bill Wilmarth
Reviewers: James Blankenhorn and Gerald Ouzounian
1. Mitigation of Sliding Motion of a Cask-Canister by Fluidstructure
Interaction in an Annular Region (wP-59208)
Tomohiro Ito, Atsuhiko Shintani, Chihiro Nakagawa, Osaka
Prefecture University; Kazuhisa Furuta, Osaka Prefcture
University (Japan)
2. Iodine Conditioning as Iodate Ion in an Apatite-Like
Ceramic (w/oP-59015)
Lionel Campayo, CEA; Danielle Laurencin, Institut Charles
Gerhardt De Montpellier; Agnès Grandjean, Institut De Chimie
Séparative De Marcoule; Remy Delorme, CEA (France)
3. Status of the Development of In-Tank/At-Tank Separations
Technologies for High-Level Waste Processing for the U.S.
Department of Energy (wP-59109)
Bill Wilmarth, SRNL; Nicholas P. Machara, US DOE Office of
Technology Innovation and Deployment; Steve P. Schneider, US
DOE Office of Waste Processing; Reid A. Peterson, PNNL;
Sheryl R. Bush, SRNL (USA)
Presentation by Jim Marra, US DOE (USA)
4. The Development, Testing and Demonstration of a New
Class of Inorganic Ion Specific Media Emphasizing the
Optimization, Stabilization and Volume Reduction of the
Final Nuclear Waste Form (w/oP-59126)
Mark Denton, Kurion Inc.; William D. Bostick, MCL, Inc.
(USA)
— BREAK —
5. High Waste Loading Glass Formulations for Hanford High-
Aluminum HLW Streams (wP-59388)
Albert Kruger, US DOE (USA)
6. The Design, Development and Demonstration of a New
Modular Vitrification System (MVS®) for the Treatment of
Nuclear Waste (w/oP-59127)
Mark Denton, Gaetan Bonhomme, Kurion Inc. (USA)
33

Thursday AM Technical Sessions
SESSION 58
Thursday: 8:30am - 12:30pm Room: 10
D&D RADIOLOGICAL CHARACTERIZATION AND
MONITORING (3.5)
Co-Chairs: Maria Lindberg, Studsvik Nuclear AB (Sweden)
Jean-Guy Nokhamzon, CEA/DEN/DADN
(France)
Organizers/Reviewers: Jas S. Devgun and Jean-Guy Nokhamzon
1. Quantifying Tc-99 Contamination in a Fuel Fabrication
Plant (wP-59024)
Pete Burgess, Nuvia Ltd; Carol Darbyshire, Springfield Fuels
Ltd (UK)
2. The Science, Assaying and Waste Sentencing of Activated
Bioshields (wP-59038)
Ian Adsley, Nuvia Limited (UK)
3. Gamma-Ray Imaging for Generating 3D Dose Rate Maps
(wP-59123)
Karl Hughes, Edmund Cracknell, Babcock International Group
(UK)
4. Sampling vs. Taking Some (wP-59349)
Dominique Francois-Bongarcon, AGORATEK International
Consultants (Canada)
— BREAK —
5. Waste Assessment: A Practical Approach to Proving Waste
Metals Suitable for Consignment as Radiologically Exempt
Materials (wP-59266)
Iain Carvel, RSRL; Richard D Gunn, Robin Strange,
Christopher Orr, Babcock International Group (UK)
6. Development of a Computer System for Support and
Documentation of Clearance of Buildings of Nuclear
Installations (wP-59278)
Christoph Winkler, Stefan Woerlen, Stefan Thierfeldt, Frank
Schartmann, Brenk Systemplanung (Germany)
7. Geostatistical Methodology for Waste Optimization of
Contaminated Premises (wP-59344)
Yvon Desnoyers, GEOVARIANCES; Didier Dubot,
CEA/FAR/USLT/SPRE/SAS (France)
8. Discrimination Monitors for Various Kinds of Waste to be
Down Graded (wP-59117)
Susumu Naito, Syuji Yamamoto, Mikio Izumi, Masamichi
Obata, Yukio Yoshimura, Jiro Sakurai, Hitoshi Sakai, Toshiba
Corporation (Japan)
SESSION 59
Thursday: 8:30am - 12:30pm Room: 6
RISK/PERFORMANCE ASSESSMENTS AND CONTAMINANT
MIGRATION (4.7)
Co-Chairs: Michel Dutzer, Andra (France)
Didier Dubot, CEA/FAR/USLT/SPRE/SAS
(France)
Organizers: Steve Brown and Didier Dubot
Reviewers: Gerd Wiatzka and Didier Dubot
1. Uncertainties on the Extension of a Polluted Zone (wP-
59198)
Chantal de Fouquet, Mines ParisTech - Ecole des mines de
Paris (France)
2. Identification and Implementation of End-User Needs
During Development of a State-of-the-Art Modeling Toolset
(wP-59069)
Roger Seitz, SRNL; Mark Freshley, PNNL; Susan Hubbard,
Lawrence Berkeley National Lab; Mark Williamson, US DOE;
Paul Dixon, LANL; Kurt Gerdes, DOE EM; Yvette Collazo , US
DOE (USA)
3. Uranium Investigation in an Alluvial Aquifer with Direct
Push Methods (w/oP-59281)
Fabian De Weirdt, Geoprobe Environmental Technologies s.a.
(Belgium)
34
4. Independent Technical Reviews for Groundwater and Soil
Remediation Projects at US Department of Energy Sites
(w/oP-59188)
Dawn Kaback, AMEC; Grover Chamberlain, DOE EM; John G.
Morse, US DOE; Scott W. Petersen, CH2M Hill (USA)
— BREAK —
5. Advanced Simulation Capability for Environmental
Management (ASCEM) (wP-59065)
Paul Dixon, LANL; Mark Williamson, US DOE; Mark Freshley,
Pacific Northwest National Lab; David Moulton, LANL; Ian
Gorton, Pacific Northwest National Laboratory; Elizabeth H.
Keating, LANL; Yvette Collazo , US DOE; Kurt Gerdes, DOE
EM; Juan Meza, Lawrence Berkeley National Laboratory (USA)
6. A Physiochemical Analysis of the Mechanisms for Transport
and Retention of Technetium (Tc-99) in Unsaturated Soils
(w/oP-59050)
Danielle P Jansik, Dawn Wellman, Elsa Cordova, DeNomy
Dage, PNNL; Dorthe Wildenschild, Oregon State University
(USA)
7. Intermediate and Long-Term Radiological Consequences of
Uncontrolled Saline Solution Access into Asse Mine
(wP-59163)
Veronika Ustohalova, Christian Küppers, Öko-Institut e.V.
(Germany)
8. Cost Benefit Assessment According to French Methodology
(w/oP-59310)
Philippe Pouget-Abadie, Pricop-Bass Tudor, URS (France)
SESSION 60
Thursday: 8:30 - 11:00pm Room: Exhibit Hall
BEST POSTERS OF ICEM 2011
Co-Chairs: Gary Benda, Bartlett Services (USA)
Dominique Greneche, Consultant (France)
Organizer: Gary Benda
This poster session highlights the top posters selected from each of the
five Tracks of ICEM 2011.

Notes
35

36
Notes

Notes
37

38
Exhibition Hours and Exhibitor Floorplan
Exhibitors Listings in Alphabetical Order
BOOTH COMPANY
217 ANDRA
ASME
320 ARS INTERNATIONAL, INC.
Sponsor Only ATOMEXPO
218 BELGOPROCESS
412 CANBERRA - AREVA
214 CEA
426 CONTAINER PRODUCTS CORPORATION
130 DEWDROPS
226 ENERGYSOLUTIONS
131 FAYAT NUCLEAR
Sponsor Only FLUOR GOVERNMENT GROUP
118 GEOVARIANCES
221 GNS GESELLSCHAFT FÜR NUKLEAR-SERVICE GmbH
112 INTERA INCORPORATED
119 ITECH-INSTRUMENTS
413 JMCS SARL
Sponsor Only KRAFTANLAGEN HEIDELBERG GmbH
125 NUCLEAR RESEARCH & CONSULTING GROUP
422 NUKEM TECHNOLOGIES GnbH
230 NUVIA GROUP
219 OECD NUCLEAR ENERGY AGENCY (NEA)
424 ONET TECHNOLOGIES
227 ORTEC (AMETEK SAS)
126 PACTEC EPS LTD
327 PORVAIR FILTRATION GROUP
127 STUDSVIK SAS
220 ROBATEL INDUSTRIES
421 RÖHR + STOLBERG GmbH
FRENCH NUCLEAR ENERGY SOCIETY (SFEN)
133 SOCODEI
117 TIB
114 URS
116 UTILIS SAS
414 WESTINGHOUSE ELECTRIC COMPANY
124 WSP ENVIRONMENT AND ENERGY

Exhibition Hours and Exhibitor Floorplan
Exhibitors Listings in Numerical Order
BOOTH COMPANY
112 INTERA INCORPORATED
114 URS
116 UTILIS SAS
117 TIB
118 GEOVARIANCES
119 ITECH-INSTRUMENTS
124 WSP ENVIRONMENT AND ENERGY
125 NUCLEAR RESEARCH & CONSULTING GROUP
126 PACTEC EPS LTD
127 STUDSVIK SAS
130 DEWDROPS
131 FAYAT NUCLEAR
133 SOCODEI
214 CEA
217 ANDRA
218 BELGOPROCESS
219 OECD NUCLEAR ENERGY AGENCY (NEA)
220 ROBATEL INDUSTRIES
221 GNS GESELLSCHAFT FÜR NUKLEAR-SERVICE GmbH
226 ENERGYSOLUTIONS
227 ORTEC (AMETEK SAS)
230 NUVIA GROUP
320 ARS INTERNATIONAL, INC.
327 PORVAIR FILTRATION GROUP
412 CANBERRA - AREVA
413 JMCS SARL
414 WESTINGHOUSE ELECTRIC COMPANY
421 RÖHR + STOLBERG GmbH
422 NUKEM TECHNOLOGIES GnbH
424 ONET TECHNOLOGIES
426 CONTAINER PRODUCTS CORPORATION
Sponsor Only ATOMEXPO
Sponsor Only KRAFTANLAGEN HEIDELBERG GmbH
Sponsor Only FLUOR GOVERNMENT GROUP
ASME
FRENCH NUCLEAR ENERGY SOCIETY (SFEN)
39

ANDRA Booth: 217
— SPONSOR —
Contact: Gérald Ouzounian
1/7, rue Jean-Monnet
92298 Chatenay Malabry, Cedex
France
Email: International@andra.fr
www.andra.fr
Andra has developed a very significant experience in the field
of management of radioactive waste, from initial design of
repositories to their closure, including siting, designing and
building of repositories, safety cases, waste acceptance and
control, monitoring during operational and postclosure phases,
and memory keeping. The agency has experience for managing
for all types of radioactive waste, from sources to high level
waste. The methods developed for managing waste include :
establishing detailed inventories, with a prospective
assessment, technical specifications for bids and contractors
selection, disposal concepts development, specifications of the
waste and their packaging (Waste Acceptance Criteria), design
and construction of repositories, safety assessment and safety
case, expertise and consultancy, including economic aspects
and review of projects and of existing facilities.
40
ASME
Contact: Vince Dilworth
Phone: U.S./Canada: +1-800-843-2763
Mexico: +001-800-843-2763
Outside North America: +1-973-882-1170
Fax: +1-973-882-1717
Email: infocentral@asme.org
www.asme.org
ASME is a not-for-profit membership organization that enables
collaboration, knowledge sharing, career enrichment, and skills
development across all engineering disciplines, toward a goal
of helping the global engineering community develop solutions
to benefit lives and livelihoods. Founded in 1880 by a small
group of leading industrialists, ASME has grown through the
decades to include more than 120,000 members in over 150
countries worldwide.
From college students and early-career engineers to project
managers, corporate executives, researchers and academic
leaders, ASME's members are as diverse as the engineering
community itself. ASME serves this wide-ranging technical
community through quality programs in continuing education,
training and professional development, codes and standards,
research, conferences and publications, government relations
and other forms of outreach.
ARS INTERNATIONAL, INC. Booth: 320
Contact: Virgene Mulligan,
Vice President, Laboratory Services
2609 North River Road
Port Allen, LA, 70767 USA
Phone: +1-800-401-4277
Fax: +1-225-381-2996
Email: marketing@amrad.com
www.amrad.com
ARS International, Inc. is a U.S. based, 8(a) Small Business
specializing in the following services: Environmental
Remediation Services; Analytical Services; Decontamination,
Deactivation Demolition Services; Field Sampling Services;
Disaster Response Services.
ATOMEXPO
— SPONSOR ONLY —
Contact: Catherine Bulgachenko
Phone: +7-495-663-38-21 (ext.152)
Fax: +7-495-663-38-20
Email: ESBulgachenko@atomexpo.com
www.atomexpo.com

BELGOPROCESS Booth: 218
Contact: Emmy Roos, Marketing and External Affairs
Gravenstraat 73
2480 DESSEL
Belgium
Phone: +32-14-33-40-08
Fax: +32-14-33-40-99
Email: emmy.roos@belgoprocess.be
www.belgoprocess.be
Founded in 1984, Belgoprocess is a limited liability company
located in the Belgium nuclear area Mol-Dessel. Belgium has
opted for a centralised processing and management of its
radioactive waste, in which Belgoprocess plays a key role. The
operational experience of Belgoprocess covers the
decommissioning of nuclear facilities, including heavily alpha
and/or beta/gamma-contaminated cells. Furthermore our
competences cover the processing of radioactive waste by
means of (super)compaction, incineration and waste water
treatment, as well as specific processes and infrastructure
developed for specific waste streams. In that perspective the
general goal is to minimize the amount of radioactive waste
produced, to maximise clearance of decontaminated material
while optimising operational costs. Belgoprocess set-up a
nuclear inventory management system supported by state of the
art non-destructive radiological waste characterisation
techniques. Currently over 50 000 drums of radioactive waste
are stored at the Belgoprocess site, from low level waste up to
high level vitrified waste. Belgoprocess offers cost effective
solutions related to radioactive waste management and
decommissioning projects.
CANBERRA - AREVA Booth: 412
Contact: Gerard Darmon, Regional Development Manager
St-Quentin-en-Yvelines
78180 Montigny-le-Bretonneux
St-Quentin-en-Yvelines
France
Phone: +33-0-1-39-48-57-76
www.canberra.com
www.areva.com
AREVA's CANBERRA brand incorporates a dozen
manufacturing and sales operations worldwide. CANBERRA
offers a wide range of measuring solutions for site safety and
occupational safety. For 40 years, CANBERRA’s operations
have been offering their expert services to the nuclear industry,
to test laboratories and to scientific research operations. The
AREVA Nuclear Measurement business unit designs and
manufactures solutions meeting the various requirements of
nuclear plant operators, including: • dosimetry and radiation
protection, • servicing of reactor components, • monitoring of
environmental impact, • materials inspection and access
control, • waste management, • decontamination and
dismantling operations. CANBERRA also provides fuel cycle
laboratories and industries a comprehensive range of solutions,
measuring devices and spectrometric analysis services.
CEA Booth: 214
Contact: Didier Dubot
18, route du Panorama - BP N°6
Fontenay-aux-Roses cedex 92265
France
Phone: +33-1-46-54-82-94
Email: didier.dubot@cea.fr
www.cea.fr
The CEA is a key player in technological research and
innovation in Europe and is active on the one hand in four
major fields: energy, defence and global security, information
technologies and health technologies, associated with
fundamental research of excellence, and on the research
infrastructures. The Clean-up Section (SAS) is a service of the
CEA of Fontenay-aux-Roses made up of project managers
which are specialized in one or several of its domains of
expertise. Their goal is to manage and proceed to the
remediation of nuclear sites, establish the radiological
characterization of contaminated sites and manage and
evacuate the nuclear waste due to the removal of the
contaminated soils. The section may intervene at a national and
an international level. Besides many publications, the Clean-up
Site Section has developed a decontamination methodology to
respond to the CEA centre’s need of dismantling all the nuclear
facilities in order to set up buildings for new research activities.
The goal of this methodology relies on various tools such as
expertise vehicles with efficient detection performances
(VEgAS), a recently developed software platform called
Kartotrak and several modules aiming at sampling
optimization, data analysis and geostatistical modeling, realtime
monitoring and validation of clean up efficiency. These
tools, used on the CEA centers, are a fitted and efficient answer
to the various needs in radiological evaluation of contaminated
sites and soils, concerning the optimization of the costs of
measurements and clean-up process on one hand, and the waste
volumes on the other hand.
CONTAINER PRODUCTS Booth: 426
CORPORATION
Contact: John Hollinden, Consulting and Sales
112 N. College Road
Wilmington, NC 28495
USA
Phone: +1-910-382-6100
Fax: +1-910-392-6778
Email: john@c-p-c.com
www.c-p-c.com
Container Products Corporation has been in the business of
supplying equipment and waste containers to the nuclear
industry since 1981. We supply containers/packaging to the
commercial nuclear world, Department of Energy Facilities,
Department of Defense facilities, and Universities. We also
have experience in design and manufacturing of hydraulic
systems such as the box and drum compaction and
decontamination units.
Our products are also sold to Canadian nuclear power
generation facilities and laboratories, and a number of foreign
countries including Europe, the Far East (Korea, Japan), South
America, (Argentina), Mexico, and Russia to name a few.
Our container product line includes IP-1, IP-2, IP-3, Type A,
(IAEA) and IATA containers in all shapes and sizes, with a
wide range of payload, lift lug, fork pocket, safety arm, hinged
lid and door options to meet most any customer needs.
We feature a full Engineering Department with a PE on staff,
and a QA Department with a NQA-1 program. We are also
qualified to Canadian QA standards, ANSI/ASME standards
and ISO 9001:2000.
41

44
F r om Nuclear P Proc
essing t o Na tur e P
reserve:
Doing the R
ight
T hings R Right
One of the world’s largest publicly traded engineering and construction
companies, Fluor is recognized for completing complex projects on schedule and
within budget.
Fluor’s reputation as a leader in environmental management and radioactive
waste management is well-established throughout the United States. Capitalizing
on our global presence and environmental expertise, Fluor is positioned to
deliver the same unparalleled level of service to our International clients, ensuring
a sustainable future.
We have the experience in project management, operations, and proven and
emerging technologies to help our customers solve complex environmental
management challenges.
Safety, Performance, and Integrity
Fluor Government Group
2300 Clarendon Blvd., Suite 1110
Arlington, Virginia 22201
703.351.1204
www.fluor.com
© 2011 Fluor Corporation. All Rights Reserved. ADGV073011

DEWDROPS Booth: 130
Contact: William Everett, President
219, ave du Maréchal Leclerc
Sin le Noble, 59450
France
Phone: +33-327-904-334
Email: dewdrops@dewdrops.fr
www.dewdrops.fr
Dewdrops provides a flexible comprehensive on-site service to
owners of wastes containing oils, solvents, organic cleaning
fluids or foams. Our patented process and mobile treatment
plants have been tailored to meet the exacting requirements of
the nuclear industry. Dewdrops aims to play a key role in
nuclear site value development by dealing economically and
safely with sensitive organic liquide waste streams or arisings.
ENERGYSOLUTIONS Booth: 226
Contact: Pippa Waterman VP, Marketing & Communications
Stella Building, Windmill Hill Business Park
Swindon SN5 6NX
United Kingdom
Phone: +44-0-1793-733100
Fax: +44-0-1793-733179
Email: international@energysolutions.com
www.energysolutions.com
EnergySolutions, headquartered in Salt Lake City, Utah, is an
international nuclear services company with operations
throughout the United States, UK, mainland Europe, Canada
and the Far East. In the UK we hold contracts with the Nuclear
Decommissioning Authority to manage the UK’s Magnox
reactor sites. We are a world leader focused on servicing the
nuclear industry with the development and implementation of
new technologies and approaches for resolving radioactive
waste challenges faced by our clients.
FAYAT NUCLEAR Booth: 131
Contact: Henri Mydlarz
3 rue René Razel
Orsay Cedex 91892
France
Phone: +33-0-1-698-56915
Email: hmydlarz@razel.fr
www.fayat.com
Founded in 1957, FAYAT is France’s leading family-owned
Group in the sector of building and industry: 2.7 billion -
turnover and more than 17 000 employees. With major
industrial facilities in Europe, Asia and America, FAYAT
regroups 118 autonomous subsidiaries in all the core
businesses of building and public works, structural steel works,
electricity, road building equipment, handling and hoisting
equipment, and pressure vessels. Several FAYAT’s Group
Companies have developed their activities in nuclear industry
with two major projects currently in progress for CEA and
EDF. RAZEL is a strong actor for civil works and turnkeys
projects, BEC brings its specialties -core sampling and wire
cutting- for dismantling in active zones, and COMETE
supplies cranes and specialized equipment for nuclear plants
and laboratories like EPR in France and China, or RJH test
reactor. All these companies have their own design capacities
and references. They can handle complex projects in
partnership with any of the other Nuclear Industry actor.
FLUOR GOVERNMENT GROUP
— SPONSOR ONLY —
Contact: Greg Meyer
2300 Clarendon Blvd, Suite 1110
Arlington, VA 22201
Phone: +1-703-647-4340
Fax: +1-703-469-1593
Email: Greg.meyer@fluor.com
Fluor is a global leader in engineering, procurement,
construction, maintenance, and project management. Active
across six continents, Fluor works with governments and multinational
companies to design, build, and maintain many of the
world's most complex and challenging capital projects. We are
a solutions-based company with the technical expertise and
financial strength to successfully complete the most difficult
assignments. Fluor is recognized around the world as a firm
that is reliable, delivers projects on time and within budget, has
an outstanding safety record, and adheres to the highest ethical
standards. Whether it's managing nuclear operations, cleaning
out and tearing down nuclear facilities, or remediating a
contaminated site, we bring leadership, experience, expertise,
respect, and pride to every effort. Headquartered in Irving,
Texas, Fluor is a FORTUNE 200 company and had revenues of
$20.8 billion in 2010.
FRENCH NUCLEAR ENERGY
SOCIETY (SFEN)
Contact: Bernard Jolly
Phone: +33-0-1-53-58-32-10
Fax: +33-0-1-53-58-32-11
Email: sfen@sfen.fr
www.sfen.org
A forward-looking learned society with high-level exchanges
on scientific and technical issues, organizing and sponsoring
large national and international events. The SFEN provides a
proactive and well-defined information policy thanks to its
widespread international presence and cooperation agreements
with learned nuclear societies.
Founding member and one of the main promoters of the
European Nuclear Society (ENS). Sustained contacts with
institutions of the European Commission and with IAEA,
working together with the French Atomic Forum and
FORATOM. SFEN makes way for the young generation and
transversal meeting groups open worldwide.
45

GEOVARIANCES Booth: 118
Contact: Jean-Jacques Peraudin, Sales Manager Environment
49bis avenue Franklin Roosevelt
AVON 77210
France
Phone: +33-1-6074-9090
Fax: +33-1-6422-8728
Email: bleines@geovariances.com
www.geovariances.com
GEOVARIANCES is a French independent software vendor
which provides the most complete solution in Geostatistics:
innovative methodologies, experts and software packages to
answer challenges in mapping, volumes estimation, risk
analysis. GEOVARIANCES develops and sells KARTOTRAK,
the first all-in-one software solution designed for the
radiological characterization of contaminated sites and
facilities. KARTOTRAK provides an integrated workflow from
in-situ characterization to final control after remediation.
GEOVARIANCES also offers consulting and training services.
GNS GESELLSCHAFT FÜR Booth: 221
NUKLEAR-SERVICE GmbH
Contact: Joerg Viermann
Frohnhauser Str. 67
45130 Essen
Germany
Phone: +49-201-109-0
Email: info@gns.de
www.gns.de
Competence for Nuclear Services: GNS Gesellschaft für
Nuklear-Service mbH, world leading supplier of casks for spent
fuel, HLW and ILW, also offers services for management and
disposal of spent fuel and all types of radioactive waste.
More than one thousand spent fuel casks of the CASTOR® and
CONSTOR® type and more than 5500 MOSAIK® casks for
intermediate level waste make GNS mbH the supplier of the
world’s top selling shielded transport and storage casks, which
are today used in a number of countries on four continents.
Design and supply of treatment facilities, decommissioning
services and all kinds of engineering support round off our
portfolio.
INTERA INCORPORATED Booth: 112
Contact: Mr. Benoît Paris
90 Av. Lanessan
69410 Champagne au Mont d'Or, France
Phone: +33-0-4-37-49-13-30
Email: bparis@intera.com
Contact: Mr. Michael Apted
3900 S. Wadsworth Blvd.
Suite 555
Denver, CO 80235, USA
Phone: +1-303-985-0005
Email: mapted@intera.com
www.intera.com
Established in 1974, INTERA has developed a solid track
record of technical excellence and client satisfaction by
providing innovative solutions to the environmental, waste
isolation and natural resource management challenges facing
industry and government.
In each of these areas, INTERA brings unique and specialized
experience that adds value to client projects. From restoring
contaminated sites like former uranium mining and processing
facilities, to developing innovative technologies to address
complex environmental issues, such as the removal of
chlorinated solvents from the subsurface, to using sophisticated
numerical models to guide site investigation and remediation
activities, INTERA is a leader in providing quantitative
geosciences and engineering services to meet environmental
challenges.
Over the past 30 years, INTERA has served as a key
contributor to high-profile underground storage projects. We
have provided long-term support for nearly all of the high-level
radioactive waste disposal programs in the U.S. and Canada,
many programs in Europe, and several in Japan.
Through this experience, our experts in hydrology,
hydrogeology, geochemistry, civil and environmental
engineering, reservoir engineering, applied statistics, and risk
and decision analysis add value to all aspects of waste isolation
and underground storage projects—from site characterization
and process modeling to risk assessment and performance
verification.
Kraftanlagen Heidelberg:
More than 40 years experience
in nuclear engineering and construction
Our services comprise of:
• Radiation protection and dismantling of nuclear facilities
• Radioactive waste management
• Nuclear power plant technology
• Plant design and process technology
• Structural analysis and system engineering
• Training and performance of high-quality welding
For Kraftanlagen Heidelberg, customer focus means maintaining
a permanent presence close to our clients, often directly,
in nuclear power stations and research centers.
Contacts:
Heidelberg headquarters
phone: +49 6221 94-07
email: info@ka-heidelberg.de
France offi ces in Manosque (ITER activities)
and St. Genis-Pouilly (CERN activities)
phone: +33 685986007
email: Breton@ka-heidelberg.de
www.ka-heidelberg.de
47

48
ITECH-INSTRUMENTS Booth: 119
Contact: Marius Casile, General Manager
ZI La Valampe - 3 av. de la Maranne
Châteauneuf Les Martigues 13220
France
Phone: +33-4-42-07-4192
Fax: +33-4-88-71-4200
Email: info@itech-instruments.com
www.itech-instruments.com
ITECH-INSTRUMENTS is a French Company specialized in
Nuclear Instrumentation. We develop our own Multi-channelanalyzers
for NaI, LaBr3,CSI scintillators, Germanium or CZT
semi-conductors. Our most famous analyzers are VENUS and
ORION. All our electronics works with the most popular
spectroscopic software INTERWINNER. ITECH-
INSTRUMENTS can design and study your systems for wastedrums
measurements, for in-situ measurements, for gloveboxes,...
ITECH-INSTRUMENTS will supply, install and test
the systems at your site or in our facility. We have Maintenance
Service and Training Team. Keep free to contact us.
JMCS SARL Booth: 413
Contact: Jacques Minassian, General Manager
8, Avenue Hoche
Saint-Remy-Les-Chevreuse 78470
France
Phone: +33-0-13047-1552
Email: jacquesminassian@orange.fr
JMCS is a distributor selling a wide range of products for the
nuclear industry, Alpha / Beta / Gamma equipments, Reactor
Outage Service Cameras, Hardened Radiation Cameras, HPGe
Spectrometer, Environmental Radiation Gamma Monitoring
station, Phantom for Whole Body Counting system Companies
represented: AHLBERG ELECTRONICS - ENVINET - LAB
IMPEX - BSI - RSD.
KRAFTANLAGEN HEIDELBERG GmbH
— SPONSOR ONLY —
Contact: Bernd Heinen
Sales and Marketing
Im Breitspiel 7
69126 Heidelberg
Phonee: +49-6221-94-1303
Fax: +49-6221-94-41303
Email: heinen@ka-heidelberg.de
www.ka-heidelberg.de
NUCLEAR RESEARCH & Booth: 125
CONSULTING GROUP (NRG)
Contact: Ronald Dekker & André Wakker
NRG, P.O. Box 25
1755 ZG, Petten
The Netherlands
Phone: +31-224-56-4234
Email: radwaste@nrg.eu
www.nrg.eu
NRG Radiation & Environment is the innovative centre of
excellence on radiological safety in the Netherlands. We can
help you use nuclear technology safely and responsibly. NRG
provides services internationally, supplying expertise and
products to protect humans and the environment from the
effects of radioactivity and radiation.
During ICEM, NRG will present new methods for treatment of
organic materials containing radioactive waste water, our waste
management database REWIND to register waste in
decommissioning projects, HIRARCHI a station to sort
different waste levels, and our services regarding natural
occurring radioactivity (NORM). We give you the full
overview of services we offer in environmental remediation
and radioactive waste management.
Our radiological protection experts provide services for:
• National and international public authorities
• Utilities
• Pharmaceutical and medical sector
• Oil and gas producers
• Scrap, ore and metal processing companies
• Airlines
Our expertise and services cover the entire spectrum of
radiological protection:
• Laboratory analysis and monitoring equipment/networks
• Dosimetry and calibration services, personal dosimetry
• Advisory services and license application support
• Risk assessment, environmental impact reports and policy
support
• Support, auditing and optimization of operations
• Training
• Ageing management and/or dismantling of radiological
facilities
• Clean-up, decontamination and recycling, waste disposal
and site declassification.

NUKEM TECHNOLOGIES Booth: 422
GmbH
Contact: Beate Scheffler,
Director Communications & Support Services
Industriestr. 13
Alzenau 63755
Germany
Phone: +49-623-9104
Fax: +49-6023-911188
Email: info@nukemtechnologies.de
www.nukemtechnologies.de
NUKEM Technologies GmbH world-wide offers nuclear
engineering solutions: • Management of radioactive waste
(from concept development to turn-key delivery of complete
waste treatment centers, techniques for all types of radioactive
waste) • Spent Fuel Management (storage technologies,
handling facilities, technologies for characterization of spent
fuel elements) • Decommissioning of nuclear facilities (from
concept development to complete project management, broad
spectrum of techniques for dismantling and decontamination) •
Comprehensive spectrum of engineering and consulting
services.
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NUVIA GROUP Booth: 230
Contact: Ron Smith, International Sales Manager
Kelburn Court, Daten Park, Risley
Warringdon, Cheshire, WA3 6TW
United Kingdom
Phone: +44-0-1925-858200
Fax: +44-0-1925-811867
Email: info@nuvia-group.com
www.nuvia-group.com
The Nuvia Group delivers to its clients a unique range of
vertically integrated solutions covering nuclear new build,
plant life extension, operations, radiation safety,
decommissioning and waste management. With a total staff of
over 1,000 it brings together the nuclear experience and
expertise of Nuvia Limited in the UK and Nuvia France with
its subsidiaries NTS, Salvarem, Mecatiss, Millennium, Essor
and Vraco as well as its international operations Nuvia India,
Nuvia Italy and Nuvia Nordic.
OECD NUCLEAR ENERGY Booth: 219
AGENCY (NEA)
Contact: OECD Nuclear Eneregy Agency (NEA)
12 boulevard des îles
Issy-les-Moulineaux 92130
France
Phone: +33-01-45-24-1015
Email: nea@oecd-nea.org
www.oecd-nea.org
The Nuclear Energy Agency (NEA) is a specialised agency of
the Organisation for Economic Co-operation and Development
(OECD). Its 30 member countries account for approximately
85% of global installed nuclear energy capacity and represent
the world?s best nuclear expertise. NEA studies are carried out
in the areas of nuclear safety and regulation, radioactive waste
management, radiological protection and public health, nuclear
science and data, nuclear development and the fuel cycle, and
legal affairs. For more information see: www.oecd-nea.org.
ONET TECHNOLOGIES Booth: 424
— SPONSOR —
Contact: Philippe Gros Gean,
Business Development Director,
Gwenaëlle Gozé, communication officer
Phone: +33-4-91-29-18-44 or +33-4-91-29-18-74
Email: pgrosgean@onet.fr or ggoze@onet.fr
www.onet-technologies.com
In a nut shell:
• Turnover: € 225 Million
• 2 300 employees
• 600 engineers & experts, 1 700 operators, technicians and
specialized site workers
• 438 employees recruited in 2010
• 3% of the turnover for R&D
Our core Business:
• Engineering & site services for nuclear power plants and
nuclear installations
• Decommissioning, decontamination & waste management
• New build
• Training
Our international network includes:
Subsidiaries in Bulgaria, India, Italy, Romania, United
Kingdom… and partners all over the world.
49

ONET TECHNOLOGIES is part of the ONET group, a
service provider with a turnover of €1.4 Billion
• 57 000 employees
• Service provider through 4 trademarks:
- ONET TECHNOLOGIES: nuclear engineering and
services
- ONET PROPRETE MULTISERVICES: cleaning
and associated services
- ONET SECURITE: guarding, electronic security
- AXXIS RESSOURCES: recruitment, temporary labour
ORTEC (AMETEK SAS) Booth: 227
Contact: Reginald Recco, Sales Manager
Elancourt 78990
France
Phone: +33-0-1-3068-89-10
Fax: +33-0-1-30-68-89-99
Email: reginald.recco@ametek.com
www.ortec-online.com
ORTEC is a leading global manufacturer of radiation detection
instrumentation offering solutions for NDA, and Waste Assay
applications including instrumentation for mobile gamma ray
assays of sites, surfaces and objects. Visit our booth to demo
the micro-trans-spec portable HPGe gamma spectrometer.
PACTECH EPS LTD. Booth: 126
Contact: Mike Nichols, Managing Director
Buttermere Pavilion, Ingwell Drive
Westlakes Science & Technology Park
Cumbria CA24 3JZ
United Kingdom
Phone: +44-0-1946-695005
Email: mikenichols@pactecinc.com
www.pacteceps.co.uk
PacTec, Inc. has over 20 years experience in manufacturing a
complete line of custom engineered packaging products for the
nuclear waste, hazardous waste, and transportation industries.
We manufacture soft sided packaging such as IP-1 and IP-2 lift
bags which meet IAEA requirements, LSA and SCO wraps,
and rail car liners and tarps. PacTec has been awarded 9
patents, and is ISO 9001-2008 certified. We also provide
product testing and development, working with our UK clients
such as LLWR, RSRL, Magnox, Dounreay, and Sellafield.
PORVAIR FILTRATION GROUP Booth: 327
Contact: Chris Chadwick
1 Concorde Close
Fareham, Hampshire PO15 5RT
United Kingdom
Phone: +44-0-1489-864330
Fax: +44-0-1489-864399
Email: info@porvairfiltration.com
www.porvairfiltration.com
Porvair Filtration Group is an international leader in the design
and supply of high quality filtration and separation materials
and products. As an engineering company we offer fully
optimised solutions to the nuclear industry including the power
generation, fuel production, reprocessing, decontamination and
waste packaging sectors. We provide everything from a single,
specialised, retrofit element to a complete packaged system
meeting the precise needs of complex applications, together
with on-site support and a complete after sales service.
50
ROBATEL INDUSTRIES Booth: 220
Contact: Christophe Bruneel, Business Manager
Rue de Genève - B.P. 203
GENAS Cedex 69741
France
Phone: +33-0-4-72-22-10-10
Fax: + 33-0-4-78-90-23-79
Email: commercial@robatel.fr
www.robatel.fr
ACTIVITIES - Turnkey contractor for major nuclear projects :
design, manufacture, and assembly of shielded laboratories for
research or production, decontamination facilities, waste
packaging facilities, nuclear fuel production, and testing
installations using glove-box technology - Design, certification
and manufacture of type B casks for transportation and storage
of radioactive materials (fuel, waste, sources): 73 type B casks
- Process equipment for reprocessing facilities -
Decommissioning projects - Development and production of -
special equipment - for the nuclear industry.

RÖHR + STOLBERG GmbH Booth: 421
Contact: Frank Köhler
Bruchfeld 52
Krefeld
Germany
Phone: +49-2151-5892-50 or
+49-170797-8939 (Mobile)
Email: frank.koehler@roehr-stolberg.de
www.roehr-stolberg.de
Calder Group is a pan-European engineering group, active in
lead engineering and the manufacture and distribution of lead
sheet. Calder is leading manufacturer of radiation shielding.
Calder Companies provide radiation shielding products,
services and solutions meeting customer demands for
applications in the nuclear power and nuclear healthcare
industry.
SOCODEI Booth: 133
Contact: Christophe Maufrais
Phone: +33-0-4-66-50-5987
Email: christophe.maufrais@socodei.fr
www.socodei.fr
SOCODEI is the French leader for short half life radioactive
waste treatment by incineration and melting.
STUDSVIK SAS Booth: 127
Contact: Thierry Hoffmann
Centre d’Affaires Euripole
ZA des Vauguillettes III – 89100 SENS
France
Phone: +3-86-66-60-75
Email: info@studsvik.fr
www.studsvik.com
MAIN ACTIVITIES - Services on the Nuclear Field :
• Processing of radioactive waste
• On-site waste services
• Engineering and consultancy
• Health physics services (manufacture and montage)
• Transport logistics
• Decommissioning services (engineering and operating)
• Operational and outage support (decontamination, nuclear
logistic)
• Fuel and materials performance
• Materials integrity and water chemistry
• Nuclear fuel analysis software
• Design and built
TIB Booth: 117
Contact: Patrick Poitevin
32 rue de Saint-Rémy
Brezolles 28270
France
Email: p.poitevin@tib.fr
Please visit our booth for more information about our services
and products.
URS Booth: 114
— SPONSOR —
Contact: Daniel Curry
Email: Daniel.Curry@wsms.comwww.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 45
countries with approximately 55,000 employees providing
services to federal, state and local governmental agencies as
well as private clients in the Energy, Industrial and
Infrastructure sectors.
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 one of the
best overall safety records in the US nuclear industry and since
1999 has brought this track record and capability to nuclear
waste programmes in the UK.
URS 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.
UTILIS SAS Booth: 116
Contact: Pascal Maloni, Sales Manager
ZAC Eurotransit - rue Mariotte
Ennery 57365
France
Phone: +33-0-87-74-60 74
Fax: +33-0-3-87-71-07-60
Email: contact@utilis.fr
www.utilis.fr
For more than 10 years UTILIS SAS has been manufacturing
rapid-deploy shelters and designing expeditionary systems for
protection of people and operational equipment. Thanks to a
large range of soft-wall and hard-wall shelters UTILIS SAS
meets requirements of both military, civil and homeland
security markets and has a history of complete equipment
solutions for various applications:
• Camps / Command Posts / Head Quarters
• CBRN decontamination of people
• CBRN collective protection
• CBRN protection for vehicles / trucks / helicopters / tanks
• Rapid deploy hangars for maintenance of aircrafts or
vehicles
• Field hospitals / First-aid Medical Posts
We offer field-proven and reliable products that meet NATO
and MIL-standard specifications and occupy a unique position
in the market place. Our shelter systems have successfully
passed snow load, solar resistance, blackout, wind, wind driven
rain resistance and durability tests at the Aberdeen Proving
Grounds (U.S. Army). To enhance your mission capabilities, a
quick and efficient service support is provided via our
international presence with head offices in Europe, US, Latin
America, Middle East and Asia.
51

URS has developed proven Integrated Management Systems that create safety conscious cultures for the highest hazard,
most complex and regulated facilities in the world. With our extensive resources, customers receive the most
comprehensive inventory of engineering, construction and management available.
The Global Management & Operations Services Group of URS provides safe, innovative management of high risk,
technically complex projects, programs and facilities for the U.S. Department of Energy and other global organisations.
Nuclear Processing/High Hazard Facilities
URS is a leader in the safe operation of high-hazard/high-consequence facilities. We have safely operated plutonium and
other complex nuclear chemical processing facilities at DOE sites across the US.
URS is part of each of the consortiums that have been awarded contracts to manage and operate the UK’s Low Level
Waste Repository and Sellafield sites by the Nuclear Decommissioning Authority.
Nuclear/Hazardous Waste
As the only company to vitrify high-level radioactive nuclear waste in the United States, URS is a world leader in safely
managing nuclear and other hazardous wastes for a wide range of federal and state agencies.
URS is the only DOE contractor successfully to licence a deep geological nuclear waste repository in the U.S. The company
oversaw the building, licensing and start up of the DOE’s Waste Isolation Pilot Plant, a transuranic waste repository near
Carlsbad, New Mexico.
Additionally, URS was the lead managemnt contractor for the licensing of Yucca Mountain.
Environmental/Facility Closure
URS is a leader in the safe and regulatory compliant closure of facilities formerly used to process and store nuclear and
other hazardous materials. URS capitalises on state-of-the-art technical knowledge backed by six decades of experience
working at nuclear facilities for commercial and government clients.
URS’s closure efforts are backed by experienced teams of professional engineers, scientists, regulatory analysts and
project managers specialising in hazardous and radiological waste engineering; soil, groundwater and mixed waste
remediation; facility decontamination and decommissioning; and environmental compliance.
Global Environmental Technology
URS has a proud history of providing advanced technological solutions. URS is a leader in the development of innovative
technologies to provide solutions to problems ranging from environmental remediation to homeland security. These
technologies range from solvent cleanup methods to waste site capping and sealing approaches.
URS also pioneered a variety of natural remedies such as phytoremediation (using natural vegetative processes),
bioremediation (using naturally occurring microbes), and monitored natural remediation (establishing a groundwater
mixing zone), to passively remove contaminants and improve the cost and effectiveness of its cleanup efforts.
53

54
FOR A HEALTHY ENVIRONMENT,
Westinghouse is
focused on
nuclear technology.
Westinghouse Electric Company is contributing to a healthy environment
as it builds new nuclear power plants that emit zero greenhouse gases when
generating electricity. Our dedication to a cleaner environment extends to
servicing existing nuclear power plants and managing by-products in an
environmentally responsible manner.
Westinghouse provides comprehensive integrated services and solutions
to the Decommissioning and Dismantling (D&D) and Waste Management
industries. We have acquired extensive experience in the dismantling of
nuclear installations from uranium mills to nuclear power plants.
We provide state-of-the-art solutions for the treatment and handling
of radioactive waste. And we offer proven solutions for the storage of
low-, intermediate- and high-level waste.
Westinghouse technology will help provide future generations with safe,
clean and reliable electricity.
Check us out at www.westinghousenuclear.com.

WESTINGHOUSE Booth: 414
ELECTRIC COMPANY
— SPONSOR —
Contact: Joseph Boucau, Director,
Global D&D and Waste Management
43, rue de l’Industrie
Nivelles 1400
Belgium
Phone: +32-67-28-84-34
Fax: +32-67-28-8534
Email: boucauj@westinghouse.com
www.westinghouse.com
Westinghouse Electric Company is a leading provider of fuel,
services, technology, plant design and equipment to utility and
industrial customers globally in the commercial nuclear electric
power industry. Nearly 50% of all commercial nuclear power
plants in operation worldwide, and approximately 60% in the
U.S., are based on Westinghouse technology. Westinghouse
supplied the original equipment design for 62 out of the 104
licensed commercial nuclear reactors in the U.S. and 113 out of
the 443 licensed commercial nuclear reactors worldwide.
Westinghouse provides global, operationally excellent nuclear
services that keep operating plants operating safely and
efficiently, as well as comprehensive, integrated services and
solutions in support of decommissioning and dismantling
(D&D) and waste management.
WSP ENVIRONMENT Booth: 124
AND ENERGY
Contact: Peter Booth
The Victoria 150-182
Salford Quays
M50 3SP Manchester
United Kingdom
Phone: +44-16-1886-2401
Email: peter.booth@wspgroup.com
www.wspenvironmental.com
WSP Environment and Energy is a global business and part of
the WSP Group building on a sound platform supporting the
nuclear and radiological sectors. We are supporting our clients
in the areas of radioactive waste management, environmental
remediation, dose and risk assessment, stakeholder
engagements, EIA and decision making processes. Drawing on
the expertise held within WSP and our delivery partners we can
provide these services across the entire nuclear fuel cycle and
NORM related industries.
Notes
55

Session 1 Abstracts
ICEM'11 Abstracts - Per instructions, only the first 200 words of each abstract is shown.
SESSION 1 — PLENARY SESSION
ABSTRACTS NOT REQUIRED
SESSION 2 — PANEL: APPROACHES FOR INTERNATIONAL COLLABORATION (5.18)
ABSTRACTS NOT REQUIRED
SESSION 3 — PANEL: LESSONS LEARNED: FUKUSHIMA, CHERNOBYL-
25 YEARS LATER, TMI-2 & OTHER EXPERIENCES (3.11)
ABSTRACTS NOT REQUIRED
SESSION 4 — NATIONAL AND INTERNATIONAL PROGRAMS FOR L/ILW MANAGEMENT (1.2)
1) LOW LEVEL WASTE DISPOSAL REGULATORY ISSUES IN THE US (w/oP-59311)
David James, Thomas Kalinowski, DW James Consulting LLC; Lisa Edwards, Electric Power Research Inst. (USA)
The United States led the international efforts to define disposal requirements for low level radioactive wastes with the publication
of US Regulations governing the disposal of such wastes. The requirements were based on a system of waste classification
based on the concentrations of certain radionuclides considered problematic for the protection of future generations from radiation
exposure. The regulation, itself, was based on a process for the development of new disposal sites defined by the US congress to
provide an equitable distribution of burden to various regions of the US. This process has met with little success in the almost 30
years since its initiation leaving only an incomplete patchwork of disposal options which are primarily dependant on the same
options that existed before the act and regulations were initiated. There is currently a new focus on the basis for some of the regulatory
requirements derived from advances in the understanding of dose impacts from certain radionuclides, improvements in performance
assessment methodologies, the increased use of engineered barriers, the reality of current disposal economies, along with
the failure of the act to conform to expectations. This paper will provide an update on the discussion taking place with a focus on
the technical considerations.
2) TAKING THE UK’S NATIONAL LLW PROGAMME FROM STRATEGY
DEVELOPMENT TO IMPLEMENTATION (w/oP-59059)
David Rossiter, Rachel O’Donnell, LLW Repository Ltd. (UK)
In 2008 UK Nuclear Waste Management Ltd (UKNWM) became the Parent Body Organisation (PBO) at the Low Level Waste
Repository (LLWR) in the UK. LLWR is the primary disposal facility for the UKs LLW, supporting a wide range of industries
across the nuclear power generation, reprocessing, defence, healthcare, education, and oil and gas sectors. One of the key tasks following
the appointment of the new PBO was to work with the Nuclear Decommissioning Authority (NDA) to develop a national
strategy for LLW generated in the UK, predominantly in the NDA estate. The new National Strategy for LLW was required to
address the gap between the forecast waste arisings and predicted capacity at LLWR.
The National Strategy for LLW Management was published in August 2010 following an 18 month development period. The
main focus of the strategy is on three areas:
• Application of the waste management hierarchy to extend the life of LLWR and ensure waste is managed in a risk-based,
fit-for-purpose manner
• Making best use of existing assets such as transport, packaging, treatment and disposal facilities
• Opening up new fit-for-purpose waste management routes to divert waste away from LLWR
Developing a robust strategy is vital to provide…
3) CEA’S WASTE MANAGEMENT POLICY AND STRATEGY. LESSONS LEARNED (w/oP-ICEM2011-59201)
Didier Dall’ava, CEA (France)
Radioactive wastes are generated during operation as well as during the decontamination and dismantling of CEAs nuclear
facility/installation. The safe and responsible management of radioactive wastes at all stages is an essential requirement of the regulatory
system. The management covers the whole sequence of operations starting with the generation of waste and ending with its
disposal. The disposal here means discarding of waste with no intention for retrieval.
It is important to note here that the safety principles and practices that are applicable during the operational phase are also applicable
during the decommissioning phase. As the radioactive waste arising is an inevitable outcome of decommissioning work, all
the regulatory requirements associated with decommissioning remain in force in waste management. This presentation deals initially
with the regulatory standards related to the management of wastes. As the management of radioactive wastes inevitably
includes treatment and conditioning of wastes, following treatment and conditioning of wastes, storage, transportation and eventual
disposal are the logical outcome of the radioactive wastes, processes are at any time improved based on the feedback experience
and the lessons learned.
4) REGULATIONS FOR THE DISPOSAL OF RADIOACTIVE WASTE IN
THE KONRAD REPOSITORY(w/oP-ICEM2011-59105)
Hagen Gunther Jung, Lower Saxony Water Management, Coastal Protection and Nature Conservation Agency
(NLWKN); Gabriele Bandt, TÜV Nord EnSys Hannover GmbH & Co. KG (Germany)
The German Atomic Act required a plan approval process to grant the license for the construction and operation of the Konrad
repository for radioactive waste with negligible heat generation (nearly analog to low/intermediate level waste).
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Abstracts Session 4
In 2002 the Ministry for Environment of the federal State of Lower Saxony licensed the construction and operation of the Konrad
repository. In addition to the Plan Approval License a Water Law Permit is required for the operation of the repository. It considers
the impact of radioactive as well as non-radioactive harmful substances on the near-surface groundwater. The Water Law Permit
limits the total maximum masses, which are allowed for the Konrad repository.
According to the Water Law Permit the operator of the repository has to register the radioactive and non-radioactive harmful
substances and to balance them. Thus, the Federal Office for Radiation Protection (BfS) as the permit holder had to develop a concept
accordingly. BfS defined threshold values for registering and balancing the harmful substances, which led to a site specific
solution for the Konrad repository.
The Lower Saxony Water Management, Coastal Protection and Nature Conservation Agency (NLWKN) as the responsible
water law regulatory authority examined this concept in order to exclude an adverse…
5) THE HYDROGEOLOGIC ENVIRONMENT FOR A PROPOSED DEEP GEOLOGIC REPOSITORY
IN CANADA FOR LOW AND INTERMEDIATE LEVEL RADIOACTIVE WASTE (w/oP-59285)
Jonathan Sykes, Stefano Normani, Yong Yin, University of Waterloo;
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 site in Ontario, Canada. The 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 the hydrogeology of the DGR
site developed through both site characterization studies and regional-scale numerical modelling analysis. The analysis provides a
framework for the assembly and integration of the site-specific geoscientific data and explains the factors that influence the predicted
long-term performance of the geosphere barrier. Flow system evolution was accomplished using both the density-dependent
FRAC3DVS-OPG flow and transport model and the two-phase gas and water flow computational model TOUGH2-MP. In the geologic
framework of the Province of Ontario, the DGR is located at the eastern flank of the Michigan Basin. Borehole logs covering
Southern Ontario combined with site specific data from 6 deep boreholes have been used to define the structural contours and
hydrogeologic properties at the regional-scale of the modelled 31 sedimentary strata that may be present above the Precambrian
crystalline basement rock. The regional-scale domain encompasses an 18,500 km2 region extending from…
6) RADIOACTIVE WASTE MANAGEMENT CHALLENGES AND PROGRESS IN IRAQ (wP-59164)
Fouad Al-Musawi, Emad Shamsaldin, Ministry of Science & Technology (Iraq);
John Cochran, Sandia National Laboratories (USA)
The government of Iraq, through the Ministry of Science and Technology (MoST) is decommissioning Iraqs former nuclear
facilities. The 18 former facilities at the Al Tuwaitha Nuclear Research Center near Baghdad include partially destroyed research
reactors, a fuel fabrication facility and radioisotope production facilities. These 18 former facilities contain large numbers of silos
and drums of uncharacterized radioactive waste and approximately 30 tanks that contain or did contain uncharacterized liquid
radioactive wastes. Other key sites outside of Al Tuwaitha include facilities at Jesira (uranium processing and waste storage facility),
Rashdiya (centrifuge facility) and Tarmiya (enrichment plant).
The newly created Radioactive Waste Treatment Management Directorate (RWTMD) within MoST is responsible for Iraqs
centralized management of radioactive waste, including safe and secure disposal. In addition to being responsible for the uncharacterized
wastes at Al Tuwaitha, the RWTMD will be responsible for future decommissioning wastes, approximately 900 disused
sealed radioactive sources, contaminated debris from the first Gulf War in 1991 and unknown quantities of NORM wastes from oil
production in Iraq.
This paper presents the challenges and progress that the RWTMD has made in setting-up a radioactive waste management program.
The progress includes the establishment of a staffing structure, staff, participation in international…
SESSON 5 — L/ILW TREATMENT TECHNOLOGY DEVELOPMENT AND IMPLEMENTATION (1.15)
1) RESEARCH AND TECHNOLOGY DELIVERY AT SELLAFIELD, UK (w/oP-59372)
Mike James, Sellafield Ltd (UK)
This paper provides an overview of research and development which is critical to the successful delivery of our operational
and clean up activities. Today we operate a number of plants supporting the nuclear fuel cycle including two reprocessing plants,
fuel fabrication and associated waste management plants for low, intermediate and high level wastes. Our decommissioning programme
is extensive with challenging and complex programmes of work along side the operational facilities. This involves a prioritised
programme to reduce risk and hazard in former reprocessing and fuel fabrication plants, fuel storage ponds and waste silos
and other related facilities.
Our work covers the span of research, development and technology transfer from investigations into low maturity applications
through to deployment of mature technologies across a range of operational and decommissioning areas. An over view of this will
be provided through examples. Characterisation is one of the key areas for successful operations in the nuclear industry today. Our
work has included commissioning work through others such as the National Nuclear Laboratory to investigate novel technologies
such as the use of muon tomography and implementing HiRad a high radiation field detector. Our work does not just include investment
in novel applications a number of significant…
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Session 5 Abstracts
2) WASTE LOADING ENHANCEMENTS FOR HANFORD LAW GLASSES (wP-59018)
Albert Kruger, US Department of Energy WTP Engineering Division (USA)
About 50 million gallons of mixed waste is currently stored in underground tanks at The United States Department of Energys
(DOE) Hanford site in Washington state. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) will provide DOEs
Office of River Protection (ORP) with a means of treating this waste by vitrification for subsequent disposal. The tank waste will
be separated into low- and high-activity waste fractions, which will then be vitrified respectively into Immobilized Low Activity
Waste (ILAW) and Immobilized High Level Waste (IHLW) products. The ILAW product is destined for disposal in an engineered
facility at Hanford site while the IHLW product will be disposed in a national geological repository. Both waste forms must meet
a variety of requirements to ensure the protection of the environment before they can be accepted for disposal.
DOE-WTP is examining options to optimize the LAW Facility and LAW glass waste form. One option under evaluation is to
enhance the waste processing rate of the vitrification plant currently under construction. It is likely that the capacity of the LAW
vitrification plant can be increased incrementally by implementation of a variety of low-risk, high-probability changes, either separately
or in combination. These changes include:…
3) THOR(R) STEAM REFORMING TECHNOLOGY FOR THE TREATMENT
OF COMPLEX AND PROBLEMATIC WASTES (wP-59084)
J. Brad Mason, Adam L. Foster, Studsvik, Inc.(USA)
Many types of complex radioactive wastes exist that, due to their chemical and radiological characteristics, are problematic to
treat using traditional methods. Studsvik has developed the THOR® process that has the capability to successfully treat a wide variety
of radioactive wastes including those with high organic content, high nitrate and nitrite content, high solids content, and heavy
metal bearing. The process produces a dry stable waste form with no liquid effluents and environmentally compliant off-gas emissions,
while reducing the overall waste volume.
The more than 10 years of successful operations at Studsviks Processing facility in Erwin, TN USA provides the foundation
for the deployment of the THOR® steam reforming process for the treatment of many complex wastes. The THOR® process has
been shown to effectively convert numerous types of U.S. Department of Energy (DOE) liquid radioactive wastes into solid products
while providing a final waste form with properties comparable to vitrified glass waste forms. In addition to testing and ongoing
project work in the U.S., multiple test programs including lab-scale and engineering-scale demonstrations have been successfully
completed for several international organizations. This international work has included testing and development work with
solid and liquid organic wastes, as well as high…
4) A ROOM TEMPERATURE STABILIZATION AND WASTE VOLUME REDUCTION METHOD
TESTED ON BELGIAN INTERMEDIATE-LEVEL HOMOGENEOUS
BITUMINIZED WASTE (EUROBITUM) (wP-59103)
Nathalie R.E.N. Impens, SCK-CEN; Jan Deckers, BelgoProcess; Lesley Adriaensen,
Pierre Van Iseghem, Studiecentrum voor Kernenergie-Centre d’Etude de l’Energie Nucléaire (Belgium)
We developed a room temperature method to recondition intermediate-level homogeneous bituminized waste, called Eurobitum.
Using this method, Eurobitum could be separated in an aqueous and an organic effluent, and a solid asphaltene-salt mix. In
this paper, we present the results of the room temperature reconditioning method using real radioactive Eurobitum samples. The
dissolution and separation processes were optimized. The residual waste could then be pressed towards a material, that might be
suitable for geological disposal. The concentration of radionuclides in the two secondary waste effluents was thereafter determined.
The aqueous effluent contained radionuclide concentrations below the treatment levels for common radioactive waste water treatment
processes, whereas the alpha radioactivity of the organic phase was low enough to consider the possibility to inject it into the
CILVA radwaste incinerator where it would undergo a thermal treatment process together with other solid radwaste. Our proposed
process could reduce the Eurobitum volume considerably. The most flammable and the least radiation resistant molecules and the
nitrates were removed from the original Eurobitum waste. Finally, the residual waste is expected to be more stable in geological
disposal conditions.
5) STANDARDIZING OF LLW/ILW TREATMENT FOR RUSSIAN
TYPE PRESSURE WATER REACTORS (w/oP-59233)
Klaus Buettner, Rainer Slametschka, NUKEM Technologies GmbH (Germany)
According to the framework program of the Russian Federation released in 2010 it is planned to build up additional nuclear
capacity of approximately 20 GWe. In addition, contracts were signed for several new-builds throughout the world. The related
design efforts together with the restricted design capacities in Russia led Rosenergoatom (Client) and Atomstroyexport (Co-Client)
to the set up of a so-called unified project TOI. TOImeans translated Technically Optimized reactor designed with Integrated databases.
NUKEM Technologies owned by Atomstroyexport was selected to develop the standardized Technically optimized design for
the treatment of the generated LLW and ILW. Special emphasis was made to reduce the waste volume for storage after treatment
to below 50 m³ per year and unit. The selected treatment technologies compromise sorting, fragmentation, thermal treatment, compaction,
evaporation, cementation etc.
In 2010 NUKEM Technologies together with Atomenergoprojekt (Main Contractor) developed the technical concept for the
treatment of liquid and solid LLW and ILW generated within the reactor as well as in the auxiliary buildings. In an iterative process
the waste amounts generated and the respective treatment methods were discussed and agreed. The next step will be to further
develop the design. The basic design (technical project) should be finalized until end of 2012.
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Abstracts Session 6
6) 35 YEARS OF INCINERATION IN STUDSVIK, LESSONS LEARNED
AND RECENT MODIFICATIONS AND IMPROVEMENTS (wP-59264)
Maria Lindberg, Karin von Kronhelm, Joakim Lövstrand, Studsvik Nuclear AB (Sweden)
In 1976 Studsvik, Sweden, started operation of its incinerator and has since been in operation. The incinerator facility is
licensed for 600 tonnes per year and during 2010 around 500 tonnes were treated.
The waste incinerated arises both in the nuclear industry, including the Studsvik site, as well as other industries where radioactivity
is used such as hospitals, universities and other research activities. Waste from customers in different countries has been treated
over the years, for example Swedish and German nuclear power plants, fuel vendors in Sweden, Germany and the UK as well
as the Studsvik site it self.
The last few years the facility waste acceptance criteria has been upgraded to also accept flame retardant plastics as well as
oils, solvents and oil soaks. In order to do this the facility it self has also been upgraded.
The latest new waste stream that can be accepted is activated carbon from off-gas treatment systems. This waste stream is treated
by grinding the pellets before incineration. A recent test has shown that this approach works really well and that the amount of
ash and dust is very small. Studsvik is currently awaiting the final authority approval for this waste stream and…
7) SODIUM-RICH WASTES: CHALLENGES, ANALYSIS AND PERFORMANCE (w/oP-59316)
Daniel Brew, Melody L Carter, Lou Vance, Martin W Stewart, ANSTO (Australia)
The immobilisation of radioactive waste is of fundamental importance to its safe management. By changing the form of the
waste, chemically and/or physically, it is possible to minimise the escape of radionuclides to the biosphere. Sodium-rich wastes can
be particularly problematic to immobilise. The high solubility of sodium in both acidic and alkaline water makes it particularly challenging
to maintain as a structural component within the wasteform matrix. Glass and glass-ceramic wasteforms have been developed
at the Australian Nuclear Science & Technology Organisation (ANSTO) that immobilise sodium-rich wastes (up to 7 M
NaOH) in accordance with US Department of Environment regulations. While traditional chemical and structural analyses such as
powder infra-red spectroscopy, thermal gravimetry and x-ray diffraction have been employed in this development, additional data
from neutron- and X-ray micro-focus tomography are also presented. These techniques were used to quantify phase volume percentage
and size distribution data to further elucidate structural information and matrix uniformity. This work presents the ANSTO
experience of sodium-rich wastes: the process involved from laboratory design with key results, to upscale considerations and challenges.
8) PRELIMINARY DEMONSTRATION OF GEOMELT TREATMENT OF
HANFORD’S K-BASIN SLUDGE (wP-59004)
Keith Witwer, IMPACT Services, Inc. (USA)
The U.S. Department of Energy (DOE) and CH2M Hill Plateau Remediation Company (CHPRC) are seeking a waste treatment
solution for sludge stored in the K-Basin spent fuel pond at the Hanford Nuclear Site, in Washington State, USA. This sludge
is a Remote Handled Transuranic (RHTRU) waste destined for final disposal at the Waste Isolation Pilot Pant (WIPP) in New Mexico.
Removal of the sludge from the K-Basin and transport for interim storage at the Hanford Site is referred to as Phase 1 in this
process. Phase 2 is defined as the treatment and packaging of the sludge such that it can be transported and disposed at the WIPP.
This paper discusses work in support of Phase 2.
ISIs GeoMelt ICV process is ideally suited to treating a heterogeneous sludge that is rich in uranium metal and which contains
a mixture of other fuel derived products, earthen materials, and miscellaneous items (operational debris, resin, etc). GeoMelt can
quickly and efficiently treat small drum load batches and will fully destroy organics, oxidize reactive metals, and permanently
immobilize radioactive constituents within a high-integrity vitrified product that will meet or exceed all WIPP acceptance criteria.
The GeoMelt Technology has an extensive experience base, having…
SESSION 6 — ISSUES AND SOLUTIONS RELATED TO SPENT FUEL, TRU, AND
HLW TRANSPORTATION AND DISPOSAL (2-5)
1) INITIAL ASSESSMENT OF RADON IN A DEEP GEOLOGICAL
REPOSITORY FOR USED NUCLEAR FUEL (wP-59145)
Kelly Sedor, Frank Garisto, Helen Leung, Nuclear Waste Management Organization (Canada)
The Nuclear Waste Management Organization is implementing Adaptive Phased Management (APM) for the long-term management
of Canadas used nuclear fuel. The APM approach encompasses centralized containment and isolation of the used fuel in
a Deep Geological Repository (DGR) in a suitable rock formation, such as crystalline rock or sedimentary rock.
During the construction and operation of a DGR, workers will be exposed to radon in air emanating from the repository host
rock. In open air, the concentration of radon gas is very small. In confined spaces, such as the DGR, radon gas has the potential to
accumulate and reach relatively high concentration levels, and may become a health hazard to workers.
An initial assessment of the radon hazard of the DGR concept was performed to determine whether there is a health hazard to
workers, and any need for radon monitoring during construction and operation.
The radon concentration in various locations was estimated based on properties of the host rock (including uranium content,
porosity and saturation), radon emanation rate, ventilation rate, and dimensions of the repository. Specifically, the analysis considered:
the radon concentration in the DGR during construction and operations; the radon concentration at the repository site,
including that adjacent to…
59

Session 6 Abstracts
2) GROUNDWATER FLOW MODELING OF PERIODS WITH TEMPERATE CLIMATE CONDITIONS FOR USE IN
A SAFETY ASSESSMENT OF A REPOSITORY FOR SPENT NUCLEAR FUEL (w/oP-59154)
Steven Joyce, Lee Hartley, Serco; Trevor Simpson, Serco (UK)
As a part of the license application for a final repository for spent nuclear fuel, the Swedish Nuclear Fuel and Waste Management
Company (SKB) has prepared a safety report (SR-Site) that assesses the long-term radiological safety after closure of a repository
located at 500 m depth in the Forsmark area, c. 120 km north of Stockholm. The movement and composition of groundwater
affect both the key pathways for radionuclide migration and the performance of engineered barriers, and hence are important issues
that have to be considered and modelled as part of quantitative assessment calculations. This presentation describes the groundwater
flow modelling studies that have been performed to represent the post-closure hydrogeological and hydrochemical situations
during temperate climate conditions, and how these are used to support safety assessment calculations and arguments.
The collation and implementation of onsite hydrogeological and hydrogeochemical data from the surface based site investigations
at Forsmark are used as the basis for defining a reference case for the natural hydrogeological situation at the site (hydrogeological
base case). Areas of uncertainty within the current site understanding and the engineered system are examined by a
series of flow model variants. The flow modelling needs to consider a wide range of…
3) CONCEPTION OF A NEW CONDITIONING PROCESS, OF STRONGLY PLUTONIUM
CONTAMINATED WASTE CANISTERS (w/oP-59205)
Maxime Michel-Noel, ONET Technologies-ONECTRA (France)
Intermediate storage in the Pegase nuclear facilities, of wastes strongly contaminated with plutonium and conditioned in 100
litres canisters, was no longer possible due to the new safety evaluation of this installation. A new process have been then imagined
to transform all these canisters in new confined packages inside the building itself. The conception, which is described, is based
on safety risk analysis which has been conducted before the construction.The operation itself is now terminated.
4) METHODOLOGICAL GUIDE ON DEVELOPMENT OF WORK PLAN FOR MITIGATION OF ACCIDENT
CONSEQUENCES DURING TRANSPORTATION OF RADIOISOTOPE THERMOELECTRIC GENERATORS AND
RADIOISOTOPE HEAT SOURCES (w/oP-59162)
Valeriy Shempelev, Scientific and Engineering Centre for Nuclear and Radiation Safety; Vladimir Reka, Rostechnadzor;
Malgorzata Sneve, Norwegian Radiation Protection Authority; Alexander Smetnik, Evgenij Kapralov,
FSUE VO “Safety”; Galina Zubareva, Tver State Medical Academy (Russia/Norway)
This methodological Guide has been built on the requirements of the regulatory acts of the Russian Federation, federal codes
and standards in the field of atomic energy, and also recommendations of the IAEA regulating the issues of safety during transportation
of radioactive material, and is intended to provide methodological aid to the operation organizations (operators), consignors
and consignees, when planning and organization of work on mitigation of accident consequences during transportation of
Radioisotope Thermoelectric Generators (RTG) and Radioisotope Heat Sources (RHS) by transport of all types, by land, air and
water all over the territory of the Russian Federation.
The methodological Guide contains recommendation on the procedure of preparation and execution of the Work Plan for mitigation
of accident consequences and its sections, as well as a standard model of the Plan and agreement with emergency and rescue
units for implementation of work to prevent transport incidents and accidents when transporting RTG and RHS drafted on the
basis of results of generalizing the real plans developed by the operating organizations. RTG utilize heat energy from radioactive
isotopes, in this case 90Sr and its daughter nuclide 90Y, to generate electricity as a power source.
5) PHYSICAL AND CHEMICAL PROCESSES DURING VACUUM DRYING
OF METALLIC SPENT NUCLEAR FUEL (wP-59114)
Martin Plys, Michael Epstein, Sung Jin Lee, Robert Apthorpe, Fauske & Associates LLC (USA)
A key process step in remediation of metallic spent nuclear fuel is vacuum drying, in order to move such fuel from pool storage
to dry storage. The drying process for metallic spent nuclear fuel is complicated by the fact that it must accommodate failed
fuel elements, scrap pieces of fuel elements, and scrap particulate. A number of physical and chemical processes that must be considered
in order to effectively and safely vacuum dry these materials are discussed in this paper including: (1) Exothermic oxidation
of exposed metallic surfaces, (2) The impact of uranium hydrides that may be present, (3) The potential for thermal instability,
(4) Degradation of thermal conductivity at low pressures, (5) Multi-component diffusion in scrap and particulate, and (6) Behavior
of uranium oxide hydrates.
We have addressed these issues by creating models for the individual phenomena that are based upon experimental data, integrating
these models into the process simulation code, FATE, and validating process simulations against closed-form solutions. The
integrated model has been employed during the conceptual and preliminary design phases for vacuum drying of scrap particulate
at Hanford in order to converge upon design and operational features that are demonstrably robust and therefore minimize safetyrelated
technical specifications
6) SECURITY ISSUES FOR LONG-TERM STORAGE OF USED FUEL (w/oP-59380)
Felicia A Durán, Gregory Wyss, Calvin Jaeger, Sandia National Laboratories (USA)
With the uncertain future of the proposed Yucca Mountain Repository for final disposal of used light water reactor fuel, the
need to store these fuels past their current regulatory certification periods has become clear. This situation presents possible regulatory
and technical issues with regard to both storage safety and security. The U.S Department of Energy (DOE), Office of Nuclear
Energy (NE) is engaged in a program to develop the technical bases for extending dry storage and subsequent transportation of used
nuclear fuel (UNF). The DOE/NE program addressing this issue is divided into four main topical areas: Research and Development
(R&D) Opportunities, Security, Transportation, and Concept Evaluations. This paper will discuss work to address security
issues for long-term storage of UNF. The timeframe for long-term management of UNF is currently defined to be on the order of
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Abstracts Session 7
300 years. This longer timeframe presents possible regulatory and technical issues with regard to both storage safety and security.
Issues associated with maintaining security for very long-term storage are being identified and addressed. An assessment has been
performed of security regulations, including those from the U.S. Nuclear Regulatory Commission and the DOE, for impacts over
the longer timeframe. The characterization of UNF as self-protecting...
SESSION 7 — NATIONAL AND INTERNATIONAL ER PROGRAMS (4.2)
1) OBJECTIVES FOR REMEDIATION OF AREAS POLLUTED BY
RADIOACTIVE SUBSTANCES IN FRANCE (w/oP-59300)
Charlotte Cazala, Didier Gay, Olivier Chabanis, Jerome Guillevic, IRSN; Odile Palut Laurent,
Geraldine Dandrieux, ASN; Alain Thomassin, IRSN/DRPH/SER/UETP; Chapalain Estelle,
Laurence Roy, Ministère de lEcologie, du Développement Durable, des Transports et du Logement (France)
In the 90s, the French administration has developed several tools in order to inventory potentially polluted sites and to identify
those requiring an immediate action. Concerns and needs have gradually moved on and a methodology for the management of
selected areas was established. A general framework was then published by the Ministry of Ecology in 2007.
The Ministry of Ecology jointly with the Nuclear Safety Authority (ASN) asked the Institute for Radiological Protection and
Nuclear Safety (IRSN) to establish guidelines for the management of radioactive polluted areas . Requirements were: i) to fit with
the published general framework while highlighting specificities of radioactive pollutants management; ii) to take benefit of
radioactive polluted areas remediation; iii) to precise remediation objectives and iv) to develop stakeholders involvement issues.
Within this general framework, two situations were identified: i) the polluted area is already used for domestic, public or industrial
purposes; ii) the polluted area is an industrial site under dismantling or a polluted wasteland where a redevelopment project is
under consideration.
Management of a polluted site with ongoing use is based on the pollution level determination. This level can be compared to
threshold values defined in applicable regulations when such threshold values do…
2) REMEDIATION OF AREVA MIRAMAS SITE (w/oP-59312)
Gilles Potier, AREVA (France)
Remediation of AREVA Miramas site
Objectives : The objectives of this project is to remediate the former facility by performing all operations useful and necessary
enabling a final withdrawal of CEA and AREVA NC companies. The desired end state is a remediated site for a new industrial use
Environmental Context : The various studies have demonstrated and confirmed the presence of soil contaminations. The types
and ranges of pollution could clearly be attributed to different historical activities : metals; mercury and organic compounds. However,
due to the different constraints (Mercury regulation, urban proximity, slick ...) and to a particular sensitivity (AREVA operator,
site located in a urban area), the project cannot be limited to the strict regulatory requirements
Description of operations : The operations concerns the remediation of approximately 100 000 m3 of soil and the decommissioning
of facilities. Soil remediation focuses on two major pollutants: mercury and organo-nitro compounds, located in areas well
identified. The techniques applied will be...
3) THE VALUE OF A MATURE, STABLE, AND TRANSPARENT REGULATORY FRAMEWORK
IN FACILITATING ER PROGRAMS LESSONS LEARNED IN DECOMMISSIONING OF
URANIUM RECOVERY AND OTHER FACILITIES IN THE USA (w/oP-59411)
Keith I. McConnell, Larry Camper, U.S. Nuclear Regulatory Commission (USA)
The history of decommissioning activities in the United States has demonstrated the value of a mature, stable and transparent
regulatory framework in facilitating the timely completion of environmental remediation. Two examples are given as case studies.
The first example relates to the history of uranium concentrate (yellowcake) production in the U.S. to support the initial development
of civilian nuclear power in the U.S. in the 1950s, 60s, 70s and 80s. This yellowcake production, which took place mostly in
the western U.S., was undertaken before laws and regulations to prevent contamination and protect public health and safety were
fully developed. Significant contamination occurred in terms of both surface and ground water contamination. Although most conventional
mills producing uranium during these early years entered decommissioning in the 70s and 80s, the vast majority are still
remediating their sites because of persistent contamination in ground water. Had an effective regulatory framework been in place,
much of this contamination would have been prevented and remediation accomplished more effectively. In contrast to this experience,
a second example is provided related to development of the regulatory framework for decommissioning of non-uranium
recovery facilities in the U.S. in the late 1990s and early 2000s. Prior to this...
4) THE FIRST NEW CONVENTIONAL URANIUM MILL IN THE U.S. IN 30 YEARS LICENSING
OF THE PINON RIDGE PROJECT, COLORADO, USA (w/oP-59330)
Steve Brown, SENES Consultants Ltd; Frank Filas, Energy Fuels Resources, Lakewood, (USA)
Energy Fuels Resources Corporation (EFR) has recently received a radioactive material license from the US State of Colorado
and intends to construct and operate a conventional acid leach uranium and vanadium mill at the Piñon Ridge Mill site in western
Montrose County, Colorado. Site facilities will include an administration building, a 17- acre mill; three tailing cells totaling 90
acres, a 40-acre evaporation pond (expandable capacity to 80 acres), a 6-acre ore storage pad, and an access road. The mill will
process ore produced from mines within a reasonable truck-hauling distance, mostly from the historical Uravan mineral belt of the
Colorado Plateau (Four Corners region of the States of Utah, Colorado, Arizona and New Mexico) and will have a capacity of 500
tons per day, but is designed to accommodate subsequent expanded production capacity of up to 1,000 tons per day. The expected
operating life of the mill is 20 to 40 years, depending on the production rate.
The Piñon Ridge mill is subject to regulation by the state of Colorado as a Agreement State with the U.S. Nuclear regulatory
Commision under the U.S. Atomic Energy Act. Accordingly, the mill license (radioactive source material license) that was issued
in January…
61

Session 7 Abstracts
5) INTEGRATED PROGRAM MANAGEMENT FOR MAJOR NUCLEAR DECOMMISSIONING
AND ENVIRONMENTAL REMEDIATION PROJECTS (w/oP-59068)
John Lehew, CH2M Hill Plateau Remediation Company (USA)
CH2M HILL Plateau Remediation Company (CH2M HILL) is the U.S. Department of Energys (DOE) contractor responsible
for the safe, environmental cleanup of the Hanford Sites Central Plateau, sections of the Columbia River Corridor and the Hanford
Reach National Monument.
The 586-square-mile Hanford Site is located along the Columbia River in southeastern Washington, 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 one of the world’s largest environmental
cleanup project.
The Plateau Remediation Contract is a 10-year project paving the way for closure of the Hanford Site. The site through its location,
climate, geology and proximity to the Columbia River in combination with the results of past nuclear operations presents a
highly complex environmental remediation challenge. The complexity is not only due to the technical issues associated with
decommissioning nuclear facilities, remediating soil contamination sites, dispositioning legacy waste and fuel materials and integrating
these with the deep vadose zone and groundwater remediation,…
6) EPRI NUCLEAR POWER PLANT GROUNDWATER PROTECTION PROGRAM (w/oP-59341)
Karen Kim, Electric Power Research Institute (USA) - Presentation by Sean Bushart, EPRI (USA)
The Electric Power Research Institute (EPRI) is a non-profit research organization that supports the energy industry. The
Nuclear Power Plant Groundwater Protection Program conducts research related to the management of groundwater at nuclear
power plant sites.
Experiences at decommissioned and operating nuclear power plants show that leaks and spills from plant systems, structures,
and components and work practices can lead to contamination on on-site soils and groundwater. While the levels of radioactivity
resulting from such contamination events do not pose health and safety threats to the public, they have raised stakeholder concerns
and, in some cases, have required remediation during decommissioning to meet site-release criteria. The EPRI Nuclear Power Plant
Groundwater Protection Program provides technical support and guidance to the industry for prevention of leaks and spills, early
detection of leaks and spills, monitoring of groundwater contamination, prevention of off-site migration of groundwater contamination,
and remediation of groundwater and soil contamination. The EPRI Groundwater Protection Program is composed of two
main objectives: 1) provide technical guidance and 2) develop advanced technologies.
The cornerstones of the EPRI Groundwater Protection Program are the EPRI Groundwater Protection Guidelines for Nuclear
Power Plants and the EPRI Groundwater and Soil Remediation Guidelines. These Guidelines documents
7) CLEAN UP STRATEGIES AND RESULTS IN USIN SITE IN SÃO PAULO CITY, BRAZIL (w/oP-59243)
Rodrigo Raposo de Almeida, Federal Fluminense University;
Valter J.G. Mortágua, Industrias Nucleares do Brasil (Brazil)
This paper presents the experience of the team of technicians and consultants from INB (Industrias Nucleares do Brazil SA)
in activities related to environmental remediation of soils contaminated by radionuclides of natural series of uranium and thorium
in the USIN unit (old mill Interlagos).
In 2007 was elaborated a master plan for remediation the USIN site, after 6 months the plan was approved by CNEN, the
nuclear regulatory agency in Brazil. Given the lack of a final deposit of radioactive residues in Brazil, the elaborate plan aimed to
minimize the volume of radioactive waste final. A criterion was developed to fractionate the tailings at three levels. The waste level
1, with activity of 226Ra and 228Ra below 0.5 Bq/g and the effective dose of less than 1.0 mSv/yr, may remain in the area. The
waste level 2, with activity of 226Ra and 228Ra than 0.5 Bq/g and individual effective dose exceeding 1,0 mSv/yr, but with total
activity below 30 Bq/g may be disposed in municipal landfills. The waste level 3, with total activity above 30 Bq/g should be stored
in steel drums of 200 liters and stored in a radioactive residues warehouse.
Considering that the time for radiometric analysis is…
8) APPLICATION OF AN ENVIRONMENTAL REMEDIATION METHODOLOGY:
THEORY VS. PRACTICE. REFLECTIONS AND TWO BELGIAN CASE STUDIES (wP-59184)
Koen Mannaerts, Stephane Pepin, Boris Dehandschutter,
Walter Blommaert, Federal Agency for Nuclear Control (FANC) (Belgium)
Like in many countries, polluted industrial sites also exist in Belgium. Although the contamination is purely chemical in most
cases, they may also contain a radioactive component. For chemically contaminated sites, extensive regulations and methodologies
were already developed and applied by the different regional authorities. However and essentially because radioactivity is a federal
competence, there was also a necessity for developing a legal federal framework (including an ER-methodology) for remediation
of radioactive contaminated sites. Most of the so-called radioactive contaminated sites are exhibiting a mixed contamination
(chemical and radiological), and hence the development of such methodology had to be in line with the existing (regional) ones
concerning chemical contamination. Each authority having their own responsibilities with regard to the type of contamination, this
makes it more complicated and time-consuming finding the best solution satisfying all involved parties. To overcome these difficulties
the legal framework and methodology - including the necessary involvement of the stakeholders and delineation of each partys
responsibilities - has to be transparent, clear and unambiguous.
Once the methodology is developed as such and approved, the application of it is expected to be more or less easy, logic and
straightforward. But is this really true? The aim this…
62

Abstracts Session 8
SESSION 8 — EXPERIENCES IN ER CLEAN-UP METHODS AND ACTIONS (4.4)
1) GROUNDWATER REMEDIATION OF HEXAVALENT CHROMIUM ALONG THE
COLUMBIA RIVER AT THE HANFORD SITE IN WASHINGTON STATE, USA (wP-59030)
Dyan Foss, CH2M Hill Plateau Remediation Company; Briant Charboneau, DOE RL (USA)
The U.S. Department of Energy Hanford Site, formerly used for nuclear weapons production, encompasses 1500 square kilometers
in southeast Washington State along the Columbia River. A principle threat to the river are the groundwater plumes of hexavalent
chromium (Cr(VI)), which affect approximately 9.8 square kilometers, and 4.1 kilometers of shoreline.
Cleanup goals are to stop Cr(VI) from entering the river by the end of 2012 and remediate the groundwater plumes to the drinking
water standards by the end of 2020. Five groundwater pump-and-treat systems are currently in operation for the remediation of
Cr(VI).
Since the 1990s, over 13.6 billion liters of groundwater have been treated; over 1,435 kg of Cr(VI) have been removed. This
paper describes the unique aspects of the site, its environmental setting, hydrogeology, groundwater-river interface, riverine
hydraulic effects, remediation activities completed to date, a summary of the current and proposed pump-and-treat operations, the
in situ redox manipulation barrier, and the effectiveness of passive barriers, resins, and treatability testing results of calcium polysulfide,
biostimulation, and electrocoagulation, currently under evaluation.
2) ENVIRONMENTAL REMEDIATION OF AN ALSTOM GRID INDUSTRIAL SITE (FRANCE) (wP-59270)
Stéphanie Romero, ALSTOM GRID (France)
ALSTOM Grid is the project owner of the remediation of a former industrial site, located in Saint-Ouen, north of Paris. The
industrial activity (power transformer production) started in 1921 and stopped in 2006. The type of pollution is linked with the former
activity. It’s an organic pollution: hydrocarbon, PCB and chlorinated volatile organic compounds. The clean-up concerns soil
and groundwater.
The main specificity of the project is that the remediation is operated inside the existing industrial buildings which must be
kept in place and restituted to the owner after the works. The treatment of soil requires excavating soil up to 9 m deep (1 m under
the level of the groundwater) inside the buildings. As a consequence, some impressive devices were set up to ensure the stability
of the buildings during the clean-up, like support structures of the foundations and strengthening of the building fronts.
In the same time, it has to be pointed out that great diversity of clean-up actions is performed on the site: the soil is excavated
to be treated on site (bioremediation or chemical treatment) or off site. The treatment of groundwater consists of pumping the oil
staying on the surface and oxidizing the dissolved pollution.
This project is probably the first experience of this scale in France with multi-contaminated soil and groundwater decontamination
in keeping and reinforcing the existing buildings.
3) DESIGN AND INSTALLATION OF A PERMEABLE TREATMENT WALL TO PASSIVELY
REMOVE STRONTIUM-90 FROM GROUNDWATER AT A FORMER COMMERCIAL
NUCLEAR FUEL REPROCESSING FACILITY IN NEW YORK (wP-59292)
Douglas Bablitch, Rupeet Malhotra, Richard Frappa, Scott Warner, AMEC Geomatrix (USA)
A permeable treatment wall (PTW) was designed and installed at the West Valley Development Project (WVDP), a former
commercial nuclear fuel reprocessing facility in New York, to passively remove and contain the expansion of strontium-90 (Sr-90)
in the site groundwater. AMEC engineers and geologists have collaborated with researchers at the State University of New York at
Buffalo (UB) and West Valley Environmental Services LLC to design and install an approximately 260 meter (860-foot) long by
0.9 meter (3-foot) thick zone of granular zeolite (a natural aggregate composed of approximately 85 percent of the mineral clinoptilolite)
that will remove Sr-90 in situ from groundwater through ion-exchange reactions. The PTW was designed to meet the functional
objectives for up to 20 years; performance monitoring will be conducted regularly and will be used to assess the lifetime efficacy
of the PTW. The zeolite-filled PTW was the selected remedial alternative due to its hydraulically passive operations and lower
life-cycle cost over other more traditional active treatment alternatives such as pump and treat.
The design relied heavily on detailed site characterization of site soils and groundwater conditions and bench and pilot scale
evaluations of various zeolite materials. The design specified the use of a one-pass…
4) DECOMMISSIONING OF THE ACTIVE STORAGE FACILITY FOR RESIDUALS IN RHEINSBERG
(BRANDENBURG/GERMANY) AND RESULTS OF GROUNDWATER MONITORING (wP-59134)
Mathias Steinhoff, Öko-Institut e.V. (Germany)
The Active Storage Facility for Residuals (Aktives Lager für Rückstände ALfR) an open air controlled area has been used
for storage of radioactive waste (liquid and solide waste) at the site of the NPP Rheinsberg in the former GDR. Liquid waste has
been cemented and dumped for near surface final disposal.
During period of operation of ALfR some incidents happened. Residues of evapo-rated cooling water of unknown amount (ca.
1-10 m³), the drop out from small leak-ages and wash off from contaminated open air storage barrels contaminated the soil.
Since 1997 the buildings of the ALfR are decommissioned and the site will be reme-diated. From the beginning of decommissioning
up to now the groundwater has been monitored.
This paper shows different steps of decommissioning and explains the experience of groundwater monitoring. Currently 33
sampling points are used for sampling groundwater of different layers. The radiological parameters under examination are Cobalt-
60, Cesium-137, Strontium-90 and Tritium. Non radiological Parameters like Bore, Potassium, Sodium, Nitrate, pH value and TOC
(total organic carbon) are also investigated.
Since 1997 activity concentration of Cobalt-60 and Tritium in groundwater has de-creased. The activity concentration of Strontium-90
had increased from 1997 to 2007. Since 2007
63

Session 9 Abstracts
5) ENVIRONMENTAL SURVEILLANCE SYSTEM FOR THE SHCHUCHYE SITE (wP-59042)
Stephane Belbeze, Matthieu Hallouin, Antea (France)
An intergovernmental agreement on cooperation about chemical weapon destruction was signed between France and the Russian
federation on 14th February 2006 in the context of a Global Partnership dedicated to preventing catastrophic terrorism and the
proliferation of weapons of mass destruction. It came into effect on 25th April 2007 after ratification by both countries. The present
demonstrated project was launched as part of this collaboration on the Shchuchye site (Russia – Kurgan Oblast). The project
concerned the environmental surveillance system for the Shchuchye site required for the safe operation of the installation used to
destroy chemical weapons.
The aim was to implement equipments and methods of analysis for very low concentrations of pollutants in the three environmental
compartments: air, water and soil. This has been achieved with the help of industry and other organizations in France (Environment/SA
for supplies, INERIS and Antea Group) and Russia (ROST Association and EKROS Engineering). This system takes
account of the normal operation of the installation as well as incident management. It includes 11 stationary atmospheric measuring
stations constructed by Environment/SA and EKROS Engineering including ASTEK dedicated toxic gas detector : “Terminator
FOV-1”, 3 mobile atmospheric measuring stations, 2 mobile soil & water measuring stations, 4 sampling cars constructed by
Environment/SA and EKROS Engineering, a complete Chemical analysis laboratory which can handle ppb analysis of toxic gases,
organics and minerals pollutants, an information collection center and a meteo station which can retrieve, display and archive all
the datas or alarm from the stationary and mobile stations. Antea Group has provided a technical expertise and various negotiations
during the negotiation phase, the project initiation files & contracts redaction, the project Monitoring and reporting to stakeholders,
the REX. Up to 2009, No other site of the world uses such an innovative system. Antea Group worked on this project for 4
years. It successfully began operating in March 2009, before the start of destruction operations, after 15 months of work on the site.
6) 25 YEARS AFTER CHERNOBYL NPP ACCIDENT: EXPERIENCE AND TRENDS OF RADIOACTIVE
CONTAMINATED SOILS REHABILITATION IN BELARUS (wP-59242)
Leanid Maskalchuk, JIPNR-Sosny NAS of Belarus (Belarus)
The paper describes the developed and applied soil decontamination measures and methods in Belarus after the Chernobyl
NPP accident. It is considered the possibility of using of organomineral amendments based on natural raw materials (sapropel)
and industrial wastes (hydrolyzed lignin, clay-salt slimes) for rehabilitation of radioactive contaminated soils.
SESSION 9 — POSTER SESSION: LOW/INTERMEDIATE LEVEL WASTE MANAGEMENT (1.1)
1) NUMERICAL MODELING FOR COLLOID-FACILITATED MIGRATION OF N-NUMBER
RADIONUCLIDES CHAINS IN THE FRACTURED ROCK (w/oP-59257)
Chun-Ping Jen, National Chung Cheng University (Taiwan)
A previous numerical model for N-member radionuclide decay chains has been extended to include the effect of radionuclide
sorption with groundwater colloids. Published distribution coefficients were employed in the nuclide decay chain to illustration the
present model. The colloid concentration was assumed constant in time and space owing to equilibrium between colloid generation
and sedimentation by chemical and/or physical perturbations. Furthermore, the diffusion of colloids into the rock matrix was
ignored because the diameter of colloid is relatively large and colloids and fracture surfaces are like-charged. The results indicated
that colloids could facilitate the transport of radionuclides and the large adsorbability of nuclides with colloids enlarged the effect
of acceleration by colloids. The influence of colloids on the radionuclide transport was expected to be crucial to the actinides with
large adsorbability; however, the present results revealed that the low-adsorbing nuclides whose parent nuclides have large capability
of sorption could be also facilitated significantly by colloids indirectly. Therefore, the role of colloids played in the transport
of the radionuclides decay chain should be assessed carefully in the radioactive waste disposal. The numerical method presented
herein is helpful to verify/validate further complex far-field models.
2) LABORATORY EXPERIMENTS ON THE ALTERATION OF HIGHLY-COMPACTED BENTONITE BY
ALKALINE SOLUTION AND THE EFFECTS ON PHYSICAL PROPERTIES (wP-59318)
Satoru Miyoshi, Shinya Morikami, Yukinobu Kimura, Tomoko Jinno, Shuichi Yamamoto, Obayashi Corporation (Japan)
The issue has to be considered for the evaluation of performance of multiple burrier systems in geological repository of
radioactive waste wheather alkaline leachate from cement matterials may alterate clay materials so that they can not show the
required performance. In order to study on the alkali alteration of compacted bentonite and the effect on the physical properties,
using modified consolidation apparatus, we have done a series of experiments for a long term such that alkali solution is injected
into compacted bentonite to measure the temporal change of swelling pressure, flow rate, and the compositions of outflow solution.
We settled two cases for the experiment: one is the case where 1.0 mol/L sodium hydroxide solution is injected (case 1) and
the other saturated calcium hydroxide solution (case 2). The dry density of specimen for both cases are 1.6 g/cm3. The dissolution
of the minerals in the high-pH environment is mainly considered in case 1 and the effect of the secondary minerals to be generated
in calcium rich environment is mainly considered in case 2. The experiment is done in the bath with constant temperature 70
celcius degree to reasonably accelerate the reaction of alkali alteration. In addition to the above measurements, a series of analysis
of solid phase is done after one and half year injection of alkaline solution. Through the experiment, we found that the dissolution
rate of montmorillonite is much lower than those of accompanying minerals and that the physical properties are reasonably kept
even though some part of the minerals are dissolved.
64

Abstracts Session 9
3) GAS TRANSPORT PROPERTIES OF PUMICE TUFF FOR PERFORMANCE
ASSESSMENT OF LLW DISPOSAL FACILITY (wP-59074)
Shuichi Yamamoto, Kenichiro Suzuki, Obayashi Corporation; Mamoru Kumagai, Japan Nuclear Fuel Limited;
Yasuhiro Tawara, Koji Mori, Geosphere Environmental Technology Corporation (Japan)
In Japan, some of the radioactive waste with a relatively higher radioactivity concentration from nuclear facilities is to be packaged
in rectangle steel containers and disposed of in sub-surface disposal facilities, where normal human intrusion is unlikely to
occur. If dissolved oxygen in pore water is consumed by steel corrosion after the closure of the facility, hydrogen gas will be generated
from the metallic waste, steel containers and concrete reinforcing bars largely by anaerobic corrosion. If the generated gas
accumulates and the gas pressure increases excessively in the facility, the facilitys barrier performance might be degraded by
mechanical influences such as fracturing of surrounding rock and cementitious materials or plastic deformation of the bentonite
buffer.
In this study laboratory experiments for gas and water transport properties of the rock were performed to evaluate gas flow
through the rock mass (pumice tuff) around a facility for low level waste disposal. Based on the experimental results two-phase
flow properties were evaluated by means of an inverse analysis method.
The pumice tuff was subjected to hydraulic conductivity tests, water retention (moisture characteristic) tests, and gas injection
tests. Non-linear properties such as relative permeability and water retention curve and hydraulic conductivity as a function…
4) EXTRACTION AND CONFINEMENT OF CAESIUM USING FUNCTIONALIZED
POROUS MATERIALS (w/oP-59106)
Carole Delchet, Guillaume Toquer, Agnès Grandjean, Institut de Chimie Séparative de Marcoule;
Joulia Larionova, Yannick GUARI (France)
An original approach to immobilize caesium species that uses hybrid functionalized porous media is presented. This study is
part of radioactive waste water treatment Indeed, one of the most abundant fission product to be extracted from radioactive effluents
are the caesium isotopes : 137Cs (T1/2 ~30y) and 135Cs (T1/2~2.106y). Transition metal hexacyanoferrates HFC (II) or (III)
exhibit better sorption properties compared to organic resins or zeolites. There are then widely studied for this application over a
wide pH range and wide range of ionic strength. Moreover, they show a good resistance to ionising radiation. First we present kinetic
and thermodynamic data of Cs sorption properties in batch experiment for pure K2Ni(FeCN) 6 , Co3 (Fe(CN) 6 ) 2 and
Ni3 (Fe(CN) 6 ) 2 . A comparison of the kinetics parameters and adsorption capacity between these HFC is then done. Furthermore,
first tests of grafting Ni3 (Fe(CN) 6 ) 2 on porous glass and ordered porous silica have allowed the extraction of Cs from an aqueous
solution. Then we show that an ammoniac atmosphere during two days at ambient temperature allows closing the porosity of
ordered porous silica. So this soft treatment will be tested with silica solids containing HFC and extracted caesium in order to immobilized
caesium species without high temperature steps, avoiding then any volatilisation.
5) PHOTOCATALYTIC AND PHOTOCHEMISTRY DEGRADATION OF LIQUID
WASTE CONTAINING EDTA (wP-59144)
Célia Lepeytre, Cyril Lavaud, Guillaume Serve, CEA Marcoule (France)
The decontamination factor of liquid waste containing 60Co is generally weak. This is due to the presence of complexant molecules.
For instance, complexation of EDTA with 60Co decreases efficiency of radioactive waste treatment. The aim of this study
was to degrade EDTA in H2O and CO2 and to concentrate free 60Co in order to increase decontamination factor. A first test of
radioactive waste treatment by photocatalysis was allowed to increase decontamination factor ( 60Co) from 16 to 196 with a device
requiring to be improved. The present work concerns the first step of the degradation process development with a more powerful
device. These first experiments were leaded to follow the only EDTA oxidation. EDTA degradation was carried out by the following
Advanced Oxidation Processes (AOP): UV/H2O2 (photochemistry); UV/TiO2 (photocatalysis); UV/TiO2 /H2O2 . A specific reactor
was achieved for this study. The wavelength used was 254 nm (UV-C). The photocatalytic degradation of EDTA was carried
out with Degussa P-25 titanium dioxide (TiO2 ), which is a semiconductor photocatalyst. The degradation degree of EDTA and the
intermediate products were monitored by TOC and ionic chromatography methods. The effects of various parameters such as pH
and the quantity of H2O2 were studied. This allows us to conclude…
6) HISTORICAL WASTE – BIOLOGICAL SHIELD & DOCUMENTATION DURING
DECOMMISSIONING (w/oP-59056)
Thomas Nellemann, Anne Sørensen, Danish Decommissioning (Denmark)
Inventory records of isotopes in radioactive waste are important as documentation with respect to governmental control, final
disposal and public transparency. We present a simple, practical and cost-effective method for characterization of a part of the
radioactive waste from decommissioning of a research reactor: The biological shielding. The method uses documentation from the
decommissioning and from the construction drawings and blueprints of the reactor as well as measurements based on samples from
the facility.
The data presented is from a 5MW experimental light water nuclear reactor (DR-2) shutdown in 1975 and decommissioned in
2008. The method incorporates an activity distribution in the biological shield. The distribution is based on measurements of samples
from across the shielding and coupled with the distance to the center of the reactor core. The exact origin of each waste item
is determined from pictures from the decommissioning and from old blueprints and construction drawings of the reactor.
The uncertainty and usefulness of the method is related directly to different factors such as: The amount of samples obtained
and the position of these with respect to the origin of the waste, the accuracy of the documentation of the decommissioning, the
size of the waste items in…
65

Session 9 Abstracts
7) A NUMERICAL INTERPRETATION OF DENSITY HOMOGENIZATION
OF BENTONITE MATERIAL IN WETTING PROCESS (wP-59153)
Atsushi Iizuka, Yusuke Takayama, Katsuyuki Kawai, Kobe University; Shinya Tachibana, Saitama University;
Shintaro Ohno, Ichizo Kobayashi, Kajima Corporation (Japan)
The bentonite material is expected to be a buffer in the nuclear waste disposal, since it has low permeability and excellent
expansion characteristics. Its expansion characteristics through wetting process can be interpreted based on the full saturation line
that is depicted as a unique line on the density and the confining pressure relationship (Kobayashi et. al., 2007). And its elasto-plastic
constitutive relation can be formulated by introducing additional irreversible strain component describing the expansion of
montmorillonite contained in the bentonite material. Its constitutive model can express the mechanical behavior of compacted bentonite
material consistently in the unsaturated sate up to fully saturated state. Then, this paper describes the density homogenization
process through a series of soil-water coupled elasto-plastic finite element simulations. Namely, we consider the cases that the
bentonite composed of two specimens having different initial densities is permeated with the constant water head. Stresses and
strains developing in the bentonite, particularly the density change of bentonite, are examined. According to a series of numerical
simulations, the density of bentonite composed of two specimens having different initial densities is not homogenized into a certain
unique value of density when the bentonite reaches fully saturated state. To confirm the simulation results, we carried out a
series of experiments. The experiment results also support our simulation results.
8) COMPARISON OF ORGANIC AND INORGANIC ION EXCHANGERS FOR THE TREATMENT OF
RADIOACTIVE LIQUID WASTES BY ION EXCHANGE PROCESSES (w/oP-59107)
Yves Barre, CEA (France)
There are number of liquid processes and wastes streams at nuclear facilities that require treatment for process chemistry control
reasons and/or the removal of radioactive contaminants. One of the most common treatment methods for such aqueous streams
is the use of ion exchange, which is a well developed technique that has been employed for many years in the nuclear industries.
Nuclear power plant process water systems have typically used organic ion exchange resins to control system chemistry to minimize
corrosion and to remove radioactive contaminant. In the past decade, inorganic ion exchange materials have emerged as an
increasingly important replacement or complement for conventional organic ion exchange resins, particularly in liquid radioactive
waste treatment and spent fuel reprocessing applications. Inorganic ion exchangers often have the advantage of a much greater
selectivity than organic resins for certain important radionuclides such as 137Cs and 90Sr. These inorganic materials have also
advantages with respect to immobilization and final disposal when compared with organic ion exchangers.
Fixed bed column experiments were carried out with porous titanium dioxide beads and with standard polystyrene divinylbenzene
resin in order to estimate the dynamics of 90Sr decontamination from a simulated liquid wastes. We present a comparison of
the kinetic and thermodynamics sorption properties between organic and inorganic ion exchangers.
9) DETRITIATION OF JET PLASMA FACING COMPONENTS (w/oP-59345)
Pierre Trabuc, Karine Liger, Nicolas Ghirelli, Christophe Perrais, CEA (France)
Beryllium tiles are proposed for ITER and the ITER-like JET wall project. The development of detritiation / recycling methods
for bulk Be and the definition of a strategy, is necessary to reduce the final waste and the constraints linked to the management
of mixed Be waste.
The tritium content in Be is the results of contribution of different mechanisms (activation, trapping in defects due to neutron
flux, and diffusion in the bulk). In fusion machines, it is foreseen to remove a part of this tritium first with in-situ detritiation techniques,
but also with ex-vessel detritiation methods. Among these methods, thermal desorption is a good candidate.
In this paper, the efficiency of thermal desorption of trapped tritium using different carrier gases is assessed. Effect of oxidant
and reductive gases on detritation of flakes (~20 GBq/g), limiter (~103Bq/g) and divertor (~104Bq/g) tiles, at relatively high temperature
(800°C), is experimentally analysed. Best results were obtained under N2 +20%O2 , after 10 h at 800°C (during 2 days) and
5 hours at 1050°C (during one day). With this treatment, it is possible to conclude that flakes, limiter and divertor tiles are allowed
as Low Level Waste (between 0.4 Bq/g and 12 kBq/g).
10) EXPERIMENTAL DROP TESTING OF WASTE CONTAINERS FOR THE KONRAD REPOSITORY (w/oP-59269)
Tino Neumeyer, Karsten Müller, Holger Voelzke, Federal Institute for Materials Research and Testing (BAM) (Germany)
The Konrad repository for not heat generating radioactive wastes was licensed in 2002 primarily. Due to legal actions the final
confirmation of this license took place not until 2007. Subsequently, the Federal Office for Radiation Protection (BfS) began scheduling
backfitting of the former iron ore mine into a repository. The licensed repository volume is 303,000 m3 considering estimations
of expected waste volumes to be disposed off. The mine itself would offer a much larger volume. Waste packages can be disposed
off as recently as the repository is ready for operation what is expected not before the end of this decade. Nevertheless, there
is high interest of qualified and certified waste conditioning and packaging for disposal today, what for from BAM and BfS tested,
evaluated and certified containers are needed.
In recent years numerous container prototypes made of steel, concrete and ductile cast iron have been tested by BAM, the Federal
Institute for Materials Research and Testing in Germany. To cover the Konrad test requirements in a conservative manner container
drop tests are performed mostly onto the unyielding IAEA target of BAMs large drop test facility instead of a representative
foundation of the repository.
This conference contribution focuses on experimental drop…
66

Abstracts Session 9
11) INSTRUMENTED MEASUREMENTS ON RADIOACTIVE WASTE DISPOSAL
CONTAINERS DURING EXPERIMENTAL DROP TESTING (wP-59142)
Thomas Quercetti, Andre Musolff, Karsten Müller,
BAM - Federal Institute for Materials Research and Testing (Germany)
In context with disposal container safety assessment of containers for radioactive waste the German Federal Institute for Materials
Research and Testing (BAM) performed numerous drop tests in the last years. The tests were accompanied by extensive and
various measurement techniques especially by instrumented measurements with strain gages and accelerometers.
The instrumentation of a specimen is an important tool to evaluate its mechanical behavior during impact. Test results as deceleration-time
and strain-time functions constitute a main basis for the validation of assumptions in the safety analysis and for the
evaluation of calculations based on finite-element methods. Strain gauges are useful to determine the time dependent magnitude of
any deformation and the associated stresses. Accelerometers are widely used for the measuring of motion i.e. speed or the displacement
of the rigid cask body, vibration and shock events. In addition high-speed video technique can be used to visualize and analyze
the kinematical impact scenario by motion analysis.
The paper describes some selected aspects on instrumented measurements and motion analysis in context with low level
radioactive waste (LLW) container drop testing.
12) REGULATORY CLEARANCE OF SPENT STEEL DRUMS (wP-59405)
Dae-Seok Hong, Korea Atomic Energy Research Institute; Young-Yong Ji, Il-Sik Kang,
Kyoung-Kil Kwak, Woo-Seog Ryu, KAERI (Korea)
At KAERI(Korea Atomic Energy Institute), radioactive soil and concrete wastes with extremely low level of activity were regulatory
cleared in 2008 and large amount of spent drums were remained. After generation, drums having good physical integrity
were reused for packaging radioactive wastes and about 50 tons of drums unsuitable for reuse were stored as radioactive wastes.
Once having been used for packaging regulatory cleared radioactive wastes, these spent drums were determined to be cleared.
Before clearance, steel drums were radiation monitored, washed with pressurized water two times, compacted and stored at a designated
area. Based on radiological dose assessment result using a clearance scenario, the clearance of steel drums was permitted
by the regulatory body. And then, treatment of the cleared drums was committed to a scrap-metal dealer for recycling. In this study,
a process of the regulatory clearance for spent steel drums and a modified radiological dose assessment model for the scrap-metal
dealer will be discussed.
13) LIQUID WASTE TREATMENT PROCESS (w/oP-59061)
Bouchta Moussaif, Touria Lambarki el Allioui, CNESTEN (Morocco)
The law defined the responsibilities of the national center of nuclear energy in Morocco CNESTEN as the sole radioactive
waste operating organization and designated CNESTEN as responsible for the management of radioactive waste at the national
level in several social and economic sectors.
The goals of the unit of radioactive waste management are: -reduce the volume of the radioactive waste product; -convert the
radioactive waste into an appropriate waste for monitoring, storage and evacuation; -Recover if it’s possible an element of value.
The Moroccan products of radioactive liquid waste per year are 0.1m3 of organic liquid and 35 m3 of liquid aqueous. The
method adopted by CNESTEN was the evaporator for liquid aqueous and the solidification with the activated carbon for the organic
liquid. An evaporation installation to treat 5 m3 of aqueous liquid in each campaign, the volume of the sludge obtained is 200
liters and 4800 liters of distillate water. Concerning the management system is plan to collect the liquid aqueous in tanks in the bottom
of each nuclear installation. After characterization according to the technical specification of radioactive waste management
nuclear installation, the waste is transported in an appropriate tank to the treatment building to be evaporated. After treatment the
clean water is collect in a separate tank waiting its discharge if it complies with the requirements of release. The volume of sludge
issued from evaporator is conditioning with mortar (40 liters) in 120liters drum, the mixing operation is ensured by shingles introduced
in the drum and the rotation of the drum is ensured by a mixer named “turn drums”. The drum must respect the acceptance
criteria before transferred to storage building. About the liquid organic waste was collected in the polyethylene move tank; this kind
of waste is mixed to an absorbent product and conditioned like the sludge.
14) CAST IRON TRANSPORT, STORAGE AND DISPOSAL CONTAINERS FOR
USE IN UK NUCLEAR LICENSED SITES (w/oP-59412)
Joerg Viermann, Matthias P Messer, GNS Gesellschaft fuer Nuklear-Service mbH (UK)
Ductile Cast Iron Containers of the types GCVI (UK trademark -GNS YELLOW BOX®) and MOSAIK® have been in use in
Germany for transport, storage and disposal of intermediate level radioactive waste (ILW) for more than two decades. In 2009 a
number of containers of these types were delivered to various Magnox sites as so called pathfinders to test their suitability for Magnox
waste streams. The results were encouraging. Therefore the Letter of Compliance (LoC) procedure was started to prove the
suitability of packages using these types of containers for the future UK Geological Disposal Facility (GDF) and a conceptual Letter
of Compliance (cLoC) was obtained from RWMD in 2010. Waste stream specific applications for Interim Stage Letters of Compliance
(ILoC) for a number of waste streams from different Magnox sites and from the UKs only pressurised water reactor,
Sizewell B are currently being prepared and discussed with RWMD.
In order to achieve a package suitable for interim storage and disposal the contents of a Ductile Cast Iron Container only has
to be dried. Mobile drying facilities are readily available. Containers and drying facilities form a concerted system.
During treatment, interim storage and transport the containers provide shielding and structural integrity….
15) OPTIMIZATION OF RADIOACTIVE WASTE CEMENTATION FOR
DECOMMISSIONING OF SALASPILS RESEARCH REACTOR (wP-59066)
Gunta Abramenkova, Maris Klavins, University of Latvia; Andris Abramenkovs,
Latvian Environment, Geology and Meteorology Centre (Latvia)
This paper deals with information on the radioactive waste cementation technology for decommissioning of Salaspils Research
67

Session 9 Abstracts
Reactor (SRR). Dismantled and segmented radioactive materials were cemented in concrete containers using tritiated water-cement
mixture. The viscosity of water-cement mortar, mechanical tests of solidified mortar’s samples, change of temperature of the samples
during solidification time and long time leakage of 137Cs, 14C, 60Co and 3T radionuclides was studied for different watercement
compositions with additives. The pH and electro conductivity of the solutions during leakage tests were controlled.
It was shown, that water/cement ratio significantly influences on water-cement mortar’s viscosity and solidified samples
mechanical stability. The role of additives – fly ash and Penetron admix in reduction of solidification temperature is discussed. It
was found, that addition of fly ash to the cement-water mortar can reduce the solidification temperature from 81oC up to 62oC. The
optimal interval of water ratio in cement mortar is discussed.
Radionuclides leakage tests show that the release curves has a complicate structure. The possible radionuclides release mechanisms
are discussed. Experimental results indicated that additives can significantly influence on the radionuclides release processes
from cemented samples.
The optimization of cementation of radioactive wastes in concrete containers was performed using mechanical stability, solidification
temperature, radionuclide releases and viscosity of mortar.
16) BAYESIAN STATISTICS APPLIED TO THE ACTIVITIES OF WASTE DRUMS (wP-59081)
Richard Bull, Ian Adsley, 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 a previous paper it was shown how simple statistical methods
could be used to make estimates of the mean activity of a set of waste drums even when the individual measurements were dominated
by limit-of-detection results. In that approach it was necessary to make assumptions about the statistical distribution (taken
to be lognormal) of the activities and the geometric standard deviations of the distributions.
In this paper a development of the method is presented which uses two statistical methods- Bayes’ Theorem and marginalization.
These allow the probability distribution of the mean activity of the waste drums to be calculated, whilst the number of assumptions
is reduced to just one, namely the form of the statistical distribution.
The mathematical details are described in the paper and the application to a set of U235-in-drum measurements is presented.
17) PHYSICAL MODELLING OF TURBULENT JETS FOR NUCLEAR SLUDGE MOBILISATION (wP-59147)
Donna McKendrick, Institute of Particle Science and Engineering; Simon Biggs,
Michael Fairweather, James Young, University of Leeds (UK)
In the UK the Office for Nuclear Regulation and the Environment Agency developed the Generic Design Assessment process
in response to a request from the UK Government. The process allows the regulators to jointly assess new nuclear reactor designs,
in advance of any site-specific proposals to build a nuclear power station.
Two reactor types are currently being assessed within Generic Design Assessment:
• AREVA and Electricité de France's UK EPR®
• Westinghouse Electric Company's AP1000®
This paper will present the outcome of the assessment of radioactive waste management within the Generic Design Assessment
process. One aspect of particular interest is the management of spent fuel from proposed new reactors as the assessment is
based on an assumption that it will be sent for disposal. Therefore the paper will specifically consider the management of spent fuel
and how this affects the regulatory decisions. The paper will look at four aspects. The first of these is to give a short overview of
the Generic Design Assessment process. This will be followed by a summary of the Generic Design Assessment Radioactive Waste
Management assessment on the acceptability of:
• The types of waste and spent fuel
• The plans for conditioning of the wastes
• The safety issues associated with short-term storage.
• The safety issues associated with long-term storage.
• The issues associated with the disposal of the wastes.
• The safety issues associated with decommissioning the reactors.
The third aspect will be to look at the work commissioned by...
18) ENVIRONMENTALLY-FRIENDLY RECOVERY OF URANIUM FROM NUCLEAR FUEL
SCRAPS GENERATED AT NUCLEAR FUEL FABRICATION PROCESS (wP-59383)
Kwang-Wook Kim, Dong-Yong Chung, Eil-Hee Lee, Keun-Young Lee, Kune Woo Lee,
Jei-Kwon Moon, Korea Atomic Energy Research Insititute (Korea)
A way to recover pure uranium as UO4 from UO2 and (U,Gd)O2 nuclear fuel scraps by using carbonate solution with hydrogen
peroxide was studied and the nuclear fuel fabrication characteristics of the UO2 powder prepared from the UO4 was evaluated.
19) SELF CLEANING HEPA FILTRATION WITHOUT INTERRUPTING PROCESS FLOW (wP-59347)
Chris Chadwick, Porvair Filtration Group (UK)
The strategy of protecting the traditional glass fibre HEPA filtration train from its blinding contamination and the recovery of
dust by the means of self cleaning, pre-filtration is a proven means in the reduction of ultimate disposal volumes and has been used
within the Fuel Production Industry.
However, there is an increasing demand in nuclear applications requiring elevated operating temperatures, fire resistance,
moisture resistance and chemical composition that the existing glass fibre HEPA filtration cannot accommodate, which can be
remedied by the use of a metallic HEPA filter media.
Previous research (Bergman et al 1997, Moore et al 1992) suggests that the then costs to the DOE, based on a five year life
cycle, was $29.5 million for the installation, testing, removal and disposal of glass fibre HEPA filtration trains. Within these costs,
$300 was the value given to the filter and $4,450 was given to the peripheral activity.
68

Abstracts Session 9
Development of a low cost, cleanable, metallic, direct replacement of the traditional filter train will the clear solution. The
Bergman et al work has suggested that a 1000 ft^3/min, cleanable, stainless HEPA could be commercially available for $5,000 each,
whereas the industry has determined that the truer cost of such an…
20) STEAM AND CONDENSATE TOLERANT HEPA FILTER - SUBSTITUTE FOR ESP (wP-59346)
Chris Chadwick, Porvair Filtration Group (UK)
A major component has failed in an active vessel ventilation system, which has been running successfully for the last 25 years
or so. The failed component is one of two Electrostatic Precipitators housed in a sealed concrete cell. The remaining running ESP
could fail at any time. The systems overall clean-up capability has to be restored. A solution has been determined by the use of a
bespoke metal filter unit. The discussion presents the issues and challenges associated with the solution.
21) STATUS OF SITE INVESTIGATION FOR L/ILW FACILITIES IN THE PHILIPPINES (wP-59262)
Maria V. Palattao, Carl Nohay, Rolando Reyes, Alfonso Singayan, Philippine Nuclear Research Institute (Philippines);
Dirk Mallants, Belgian Nuclear Research Centre SCK-CEN (Belgium)
Radioactive waste in the Philippines is generated from the various applications of radioactive materials in medicine, industries
and research. The Philippine Nuclear Research Institute (PNRI) currently manages these wastes through its centralized treatment
and storage facilities on site. Radioactive wastes that are received at the Institute are of different types ranging from contaminated
solid and liquid materials to spent sealed sources, including radium. Treated and conditioned wastes are temporarily stored in simple
roofed above ground concrete bunkers. The Philippine government through the Inter-agency Subcommittee on Radioactive
Waste Management is committed to the development of a national repository for the countrys radioactive waste. This policy has
been recognized in spite of the relatively small volume of radioactive waste compared with countries that have a nuclear power program.
To date, a potential site has been identified for detailed investigation with the assistance of the International Atomic Energy
Agency (IAEA). The site is located in the northern part of the Philippine archipelago and has about 34 hectares for potential development.
A drilling program that aimed to investigate the geologic, hydrogeologic and hydrologic properties of the site has been
implemented. All boreholes have been equipped with piezometer wells to continuously monitor the seasonal variation…
22) MANAGEMENT OF SMOKE DETECTORS CONTAINING RADIOACTIVE SOURCES (wP-59049)
Mercedes Salgado Mojena, Juan Carlos Benitez Navarro, Juan Miguel Hernandez García, Rafael Castillo Gomez,
Ania Berdellans Escobar, CPHR (Cuba); Carlos Jose Pirez, Pedro Graciano Soto, Atomic Centre Ezeiza,
National Commission of Atomic Energy (Argentina)
Ionic smoke detectors contain radioactive sources that could be of Am-241, Pu-238, Pu-239, Kr-85, or other radionuclides.
Although the activity of these devices is very low, their distribution and use is under regulatory control, and when become disused,
should be managed as radioactive waste. More than 25 000 smoke detectors have been collected and stored at the Centralized Waste
Management Facility in Cuba.
The safe management of ionic smoke detectors consists in dismantling the devices, recovering the radioactive sources and conditioning
them for long term storage and future disposal. Most of smoke detectors contain long lived radioactive sources (Am-241,
Pu-238 and Pu-239), therefore especial attention is given to the management of these sources. The rest of nonradioactive materials
are segregated (plastic, metal and electronic components) for recycling. A technical manual with specific instructions for all operations,
including dismantling of detectors, segregation and management of non-active parts, recovering and conditioning of radioactive
sources, has been developed.
23) CURING TIME EFFECT ON THE FRACTION OF 137CS FROM IMMOBILIZED
RADIOACTIVE EVAPORATOR SLUDGE BY CEMENT (wP-59006)
Ilija Plecas, Slavko Dimovic, Vinca Institute of Nuclear Sciences; Radojica Pesic, Nuclear Facilities of Serbia (Serbia)
Traditional methods of processing evaporator concentrates from NPP are evaporation and cementation.These 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. The
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.
Key words : Cement, Radioactive Waste, Radionuclide, Leaching, concrete
24) AN APPROACH FOR THE DEVELOPMENT OF A COMPREHENSIVE DATA BASE OF TIME-DEPENDENT
HYDRAULIC AND TRANSPORT PARAMETERS FOR CONCRETE ENGINEERED BARRIERS (wP-59299)
Suresh Seetharam, Dirk Mallants, Janez Perko, Diederik Jacques, SCK.CEN (Belgium)
This paper presents an approach for the development of a comprehensive data base of time-dependent hydraulic and transport
parameters for concrete engineered barriers and multi-layer cover of the future Dessel near surface repository. The parameter derivation
is based on an extensive literature review, experimental data from studies on cementitious materials specific for the Dessel
repository and numerical modelling studies. Best estimate parameter values for assessments are derived; source range and expert
range are also determined, together with probability density functions. Emphasis is also given to the upscaling of laboratory derived
parameter values to the repository component scale resulting in large-scale effective parameters. To accommodate different levels
of conservatism in the various assessment calculations defined by ONDRAF/NIRAS, several sets of parameter values have been
derived based on assumptions that introduce different degrees of conservatism. For pertinent parameters, the time evolution of such
properties due to the long-term concrete degradation is also addressed. The implementation of the approach is demonstrated by considering
diffusion coefficient as an example.
69

Session 10 Abstracts
25) RADIATION PROTECTION EXPERIENCES IN RETRIEVAL OF RADIOACTIVE
WASTE AT PÜSPÖKSZILÁGY REPOSITORY (wP-59054)
László Juhász, National Research Institute for Radiobiology and Radiohygiene; Sándor Kapitány,
István Barnabás, Public Limited Company for Radioactive Waste Management;
Anna Mária Motoc, National Research Institute for Radiobiology and Radiohygiene (Hungary)
The radioactive waste disposal facility at Püspökszilágy is declared for disposal of institutional radioactive waste from smallscale
producers in Hungary run by the Public Limited Company for Radioactive Waste Management (PURAM). The repository was
sited in 1971 and commissioned in 1976. The repository is a typical near-surface facility, composed of concrete vaults and special
disposal units.
Because the original licence did not deal with waste acceptance criteria high activity sources and spent sealed radioactive
sources (SSRS) consisting of long-half life and alpha emitting radionuclides were also disposed of. The results of the safety assessments
clearly indicate that the SSRS could result in high doses to individuals who intrude into the facility after the closure and they
could also lead to high doses following any future disruption of the facility by natural processes. Therefore the PURAM launched
a demonstration program for retrieval and removal these radiation sources.
The main aim of the achievement of the demonstration program was that each step of the recovery technologies could be appropriately
tested before starting the full scale retrieval program. Concerning the high level activities of radiation sources and much
elevated radiation fields the demonstration program had to be concerned from the radiation protection…
SESSION 10 — PANEL: EMERGING ISSUES IN THE MANAGEMENT OF I/ILW (1.16)
ABSTRACTS NOT REQUIRED
SESSION 11 — PANEL: HOW CAN NETWORKS IMPROVE THE IMPLEMENTATION OF ER PROJECTS?
THE IAEA NETWORK ON ENVIRONMENTAL MANAGEMENT AND REMEDIATION-ENVIRONET (4.15)
ABSTRACTS NOT REQUIRED
SESSION 12 — WASTE MINIMIZATION, AVOIDANCE, AND RECYCLING (1.3)
1) WASTE MINIMIZATION BY MELTING - RECYCLING OF RADIOACTIVE METALS (wP-59040)
Thomas Kluth, Ulrich Quade, Siempelkamp Nukleartechnik GmbH (Germany)
Preserving resources is the fundamental principle for recycling of waste metals, using it as raw material for new products.
Recycling radioactive metal waste from operational and decommissioned nuclear facilities meets this principle and minimizes the
volume of radioactive waste and consequently saves costs.
For 20 years now, the operation of the melting plant CARLA (Centrale Anlage zum Recyclieren Leichtaktiver Abfälle / central
plant for recycling slightly radioactive waste) alongside the production facilities of the Siempelkamp foundry have delivered
this service with plant licensed for handling radioactive material according to § 7 StrlSchV (the German radiation protection ordinance).
The flexible nature of the facilities and products even allow metals that cannot be released after the primary melt, to be
recycled into components used in nuclear industry, e. g. waste containers made of cast iron or heavy concrete. These recycling
routes are unique in the world and were developed by Siempelkamp in the 1980ies and have been expanded continuously since
then.
More than 5,500 waste containers manufactured from Ductile Cast Iron (DCI) in cylindrical or cubic form licensed for the German
ILW waste repository KONRAD have been manufactured with a recycled metal content of between 15 % and 25 %. Waste
metals…
2) WASTE MINIMIZATION BENEFITS OF DISSOLVABLE PROTECTIVE CLOTHING (wP-59003)
Michael Cournoyer, David Wannigman, Robert Dodge, Los Alamos National Laboratory (USA)
Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA-55) involve working with various
amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne
contamination, and excursions of contaminants into the operators breathing zone are controlled through the radiological protection
program. A key element of this program is the proper selection of protective clothing. Re-useable, launderable protective
clothing has been the standard for several decades. Over the years, radioactive waste disposal costs have increased and disposal
options have become more limited. This has prompted the development of single-use, dissolvable protective clothing. Single-use,
dissolvable protective clothing is under evaluation as a replacement for launderable woven textile garments at TA-55. We examined
re-useable, launderable and single-use, dissolvable protective clothing, addressed management issues (residual contamination,
cost, environmental footprint, quality assurance), and waste minimization benefits. Replacement of launderable garments with single-use,
dissolvable protective clothing improves the safety configuration of TA-55 by reducing LLW waste generation. Process
improvements of this type contribute to LANLs scientific and technological excellence by increasing the Laboratorys operational
safety.
3) EVALUATION OF EXTERNAL EXPOSURE DURING BUILDING AND OPERATION OF CONCRETE BRIDGES
CONSTRUCTIONS THAT REUSE THE CONDITIONALLY RELEASED STEELS (wP-59120)
Michal Panik, Vladimir Necas, Slovak University of Technology (Slovakia)
This paper presents ongoing results of the project presented at ICEM`10 related to the topics of reusing the conditionally
released materials from decommissioning. The subject of the reuse of conditionally released materials in this case is modeling of
bridge constructions which reuse the conditionally released steel in the form of reinforcement bars for the concrete bridges. A general
approach for the project was presented at ICEM`10. The activities of the project continue in evaluating the individual effective
doses from the external exposure based on reused conditionally released steels separately for public and for professionals (the inter-
70

Abstracts Session 12
nal exposure will be evaluated in next stages of the project). Evaluated scenarios are related to critical groups of professionals constructing
the bridges (workers scenarios). The computer code VISIPLAN 3D ALARA 4.0 planning tool was used for the calculation
of the individual effective dose for professionals. Various limits of the annual individual effective dose are used for the evaluation
of calculation results. The aim of the ongoing modeling is to develop a set of data of maximal radioactivity concentration for
individual radionuclides in the conditionally released steel used in the bridges model constructions in order not to exceed the limits
for the individual effective dose.
4) TREATMENT OF SPENT ACIDIC DECONTAMINANTS WITH A HIGH-EFFICIENCY
CEMENTATION METHOD (wP-59063)
Kou-Ming Lin, Ching-Tu Chang, Ming-Shin Wu, Wen-Chen Lee,
Jen-Chieh Chung, Tsong-Yang Wei, Institute of Nuclear Energy Research (Taiwan)
Metal scrap is a major waste generated from the decommissioning of nuclear facilities. Through a decontamination process,
most of the metal scraps can be cleaned to meet the clearance level, which can then be reused or released according to the regulatory
procedure. Usually, chemical processes will be used in the cleaning step. Phosphoric acid and fluoroboric acid are the typically
used chemicals or decontaminants. Although the regeneration method could be applied to increase the lifetime of the decontaminant,
its decontamination efficiency would decrease after 3 to 5 cycles. In addition, the contaminated nuclide such as Cs-137 is not
easily removed during the regeneration process; it tends to accumulate slowly in the decontaminant. According to the ALARA principle,
decontaminant must be replaced if its activity exceeds the regulatory level. As a result, significant amount of spent strong
acid solution would be generated. The traditional way of treatment is to neutralize the acid solution with an alkaline solution. However,
such method will produce large amount of sludge that requires further stabilization, which offsets the advantages of metal
decontamination.
A high-efficiency solidification method is developed and used to treat the spent phosphoric acid and fluoroboric acid solution
in INER. The self-polymerization nature of
5) METHODOLOGY FOR IDENTIFICATION OF CONDITIONALLY RELEASED MATERIALS FROM
DECOMMISSIONING USING THE OMEGA CODE (wP-59175)
Matej Zachar, Vladimír Daniaka, DECOM, a.s.; Vladimir Necas, Slovak University of Technology (Slovakia)
The nuclear facility decommissioning process is characterized by production of large volume of radioactive materials to be
managed. The materials with radioactivity slightly above the defined unconditional clearance levels could be released conditionally
for a specified industrial application in accordance with beforehand developed scenario ensuring that the limits for radiation
exposure of workers and public will not be exceeded.
The paper presents the methodology for identifying and assessment of the physical and radiological parameters of material
items suitable for using in defined scenarios of conditional reuse of materials resulting from the decommissioning process. The calculation
of mentioned parameters is done by using the analytical code OMEGA with implemented calculation stream for evaluation
the conditional release process.
The necessary input parameters for the OMEGA code are maximum concentrations of each radionuclide in the conditionally
released materials which do not cause the doses above the limit values for the possible scenarios of further use of materials outside
the nuclear site. The examples of such scenarios are assessed and presented in other related papers proposed for the ICEM conference.
Based on the inventory database of physical and radiological characteristics of decommissioned facility, the calculation algorithm
separates the relevant material items with activity concentrations…
6) IMPACT OF NUCLIDE VECTOR COMPOSITION CONTAINED IN CONDITIONALLY
RELEASED STEEL REUSED IN MOTORWAY TUNNELS SCENARIO ON
CALCULATED INDIVIDUAL EFFECTIVE DOSES (wP-59128)
Tomas Hrncir, Vladimir Necas, Slovak University of Technology (Slovakia)
This paper presents ongoing results of the project presented at ICEM 10 [paper 40071] related to the topics of the reuse of conditionally
released materials arising from decommissioning of nuclear installations.
The subject of the presented paper is modelling of motorway tunnels, which reuse the conditionally released steel in form of
reinforcing nets and bars for the concrete construction of tunnels. The general approach for the project was presented at ICEM 10.
The activities of the project continued in evaluating the impact of the nuclide composition contained in the conditionally released
steel on calculated individual effective doses from the external exposure (the internal exposure will be evaluated in next stages of
the project). Mentioned radioactive steel arises during decommissioning and would be reused in motorway tunnels. Evaluated scenarios
are related to critical groups of public (drivers scenarios) and for professionals constructing the tunnels and performing the
maintenance of tunnels (workers scenarios).
The computer code VISIPLAN 4.0 3D ALARA planning tool was used for the calculation of individual effective doses for
worker and for public groups. Various limits of the individual effective dose are used for public and for professionals. The aim of
the ongoing modelling is to develop a set…
7) EVALUATION OF TECHNICAL, ECONOMIC AND FINANCIAL FEASIBILITY FOR RECYCLING
AND REPROCESSING OF RADIOACTIVE WASTE FROM A REMEDIATION WORK OF LOW
AND MEDIUM ACTIVITY FOR THE EXTRACTION OF HEAVY MINERALS (w/oP-59231)
Rodrigo Raposo de Almeida, Federal Fluminense University;
Valter J.G. Mortágua, Industrias Nucleares do Brasil (Brazil)
This paper aims to present the methodology and criteria used for the destination, discard and reuse of waste from the remediation
activities of soil contaminated by radioactive waste of low activity in the USIN Plant. The site is located in São Paulo city,
the city with the largest population of Brazil, with approximately 11 million inhabitants. As the environmental agency in São Paulo
state, in this neighborhood there are several cases of severe contamination of soil and groundwater. The situation of contamination
is so severe that it is forbidden the use of groundwater in the region for an indefinite period. Site of the plant running in a monazite
71

Session 13 Abstracts
processing plant for extraction of rare earths, have been filed across the land several fractions of soil containing monazite sand. In
order to guide the remediation of the area for unrestricted use, was a plan for remediation of radioactive waste characterization
based on geological, hydrogeological and environmental extensive in the area. From the calculation of the dose was established that
the fractions of soil with concentrations of 226Ra and 228Ra below 0.5 Bq/g result in additional effective dose less than 1.0 mSv/yr
and therefore can be kept on the ground. The fractions…
8) WNA STATEMENT - TOWARDS GREATER EFFICIENCY IN THE MANAGEMENT
OF LOW-LEVEL RADIOACTIVE MATERIAL THAT CONCURRENTLY SUPPORTS REUSE,
RECYCLING AND DISPOSAL (wP - 59414)
Sylvain Saint-Pierre, World Nuclear Association (WNA) (UK)
This paper presents the subject WNA statement which resulted from a conserted effort between a wide range of nuclear industry
players such as nuclear power utilities, nuclear fuel cycle companies – and experienced recyling and waste disposal companies
which routinely received material from nuclear sites.
SESSION 13 — HLW, FISSILE, TRU AND SPENT FUEL SHORT AND LONG-TERM STORAGE ISSUES (2.4)
1) WEST VALLEY DEMONSTRATION PROJECT HIGH LEVEL, TRANSURANIC,
AND GREATER THAN CLASS C WASTES (wP-59048)
James Blankenhorn, West Valley Environmental Services (USA)
Located in the scenic hills of Western New York, just about 35 miles south of Buffalo, the 68 acre West Valley Demonstration
Project (WVDP) is a unique and challenging environmental cleanup project that currently manages High Level, Transuranic, and
Greater than Class C wastes
Before the U.S. Department of Energy (DOE) took on the challenge of cleaning up the site, the site was the location of the only
commercial spent nuclear fuel (SNF) reprocessing facility to operate in the United States. Operated by Nuclear Fuels Services from
1966-72, the site was owned by the State of New York and licensed by the Atomic Energy Commission. During operations, the
plant reprocessed approximately 640 metric tons of spent nuclear fuel. When commercial operations were discontinued and the
facilities were returned to New York State, there were nearly 2,271,247 liters (nearly 600,000 gallons) of liquid high-level radioactive
waste (HLW) in an underground storage tank and the facility that was used to reprocess the SNF, the Main Plant Process Building
(MPPB), was highly contaminated.
The West Valley Demonstration Project Act of 1980 (the Act) authorized DOE to conduct a cleanup of the site, in cooperation
with the New York State Energy Research and Development…
2) MANAGING AGING EFFECTS ON USED FUEL DRY CASK FOR VERY LONG-TERM STORAGE (wP-59067)
Omesh Chopra, Dwight Diercks, David Ma, Vik Shah, Shiu-Wing Tam, Ralph Fabian,
Yung Liu, Mark Nutt, Argonne National Laboratory (ANL)(USA)
The cancellation of the Yucca Mountain repository program in the Unites States raises the prospect of very long-term storage
(i.e., >120 years) of used fuel and deferred transportation. While long-term storage of used nuclear fuel in dry cask storage systems
(DCSSs) at Independent Spent Fuel Storage Installations (ISFSIs) is already a standard practice among U.S. utilities, recent rulemaking
activities of the U.S. Nuclear Regulatory Commission (NRC) indicated additional flexibility for the NRC licensees of ISF-
SIs and certificate holders of the DCSSs to request initial and renewal terms for up to 40 years. The proposed rule also adds a
requirement that renewal applicants must provide time-limited aging analyses (TLAAs) and descriptions of aging management programs
(AMPs) to ensure that the systems, structures, and components (SSCs) in the DCSSs will perform as designed under the
extended license terms. Details of the license renewal process can be found in the NRC draft Standard Review Plan (NUREG-1927)
for renewal of ISFSI Licenses and DCSS Certificates of Compliance (CoCs). The final Standard Review Plan will provide NRC
staff with guidance on the renewal of site-specific licenses and CoCs.
Over the last three decades, Argonne National Laboratory has conducted research programs funded by NRC to address…
3) APPLICATION OF COUPLED THERMO-HYDRO-MECHANICAL-CHEMICAL (THMC) PROCESS IN
HYDROTHERMAL SYSTEMS TO PROCESS NEAR A HIGH-LEVEL NUCLEAR WASTE REPOSITORY (wP-59246)
Geoffrey Peter, Oregon Institute of Technology Portland Center (USA)
Modeling of coupled processes in the geology near a high-level nuclear waste repository is similar to the modeling of coupled
Thermo-Hydro-Mechanical-Chemical (THMC) processes that occur in magma-hydrothermal systems. Magma-hydrothermal systems
were extensively studied by former Professor Denis Norton and his colleagues at the Geoscience Department at University of
Arizona. These hydro-thermal codes were verified by obtaining excellent matches between calculated oxgyen 18 isotope - values
and measured oxygen 18 isotope values in three principal rock units: basalt, gabbro, and gneiss.
This paper reviews the concept of transport theory used in the formulation of the conservation principle that is used to model
the hydrothermal systems. In addition, it reviews conservation of mass, momentum, energy, and chemical components equations as
applied to the multicomponent-multiphase systems related to hydrothermal systems and obtains parallels to reaction rates and
radionuclide transport in the geology of a high level nuclear water repository. The paper discusses the numerical methods used to
solve the coupled equations.
Further, this paper compares published results obtained by other researchers modeling coupled THM process in the geology of
high-level nuclear waste repositories.
72

Abstracts Session 13
4) GENERIC DESIGN ASSESSMENT OF LONG-TERM SPENT FUEL STORAGE
FOR NEW REACTORS IN THE UK (wP-59174)
Christopher Fisher, Nuclear Directorate, Health and Safety Executive;
Dave Watson, Office of Nuclear Regulation; Ian Streatfield, Colette Grundy,
Saffron Price-Walter, Environment Agency, Dave Glazbrook, Office of Nuclear Regulation (UK)
In the UK the HSE and the Environment Agency developed the Generic Design Assessment or GDA process in response to a
request from the UK Government. The process allowed the regulators to jointly assess new nuclear reactor designs, in advance of
any site-specific proposals to build a nuclear power station. The first GDA process will be complete in June 2011.
Two reactor types are being assessed within GDA:
• AREVA and Electricité de France’s (EDF) UK EPR®
• Westinghouse Electric Company’s AP1000®
This paper will present the outcome of the assessment of radioactive waste management and decommissioning (RW&D)
within the GDA process. One of the most interesting aspects is the management of spent fuel as it is assumed that this will be
sent for disposal. Therefore the presentation will specifically consider the management of spent fuel and how this affects the
reulatory decisions.
The presentation and paper will look at four aspects. The first of these is to give a short overview of the GDA process.
This will be followed by a summary of the regulators conclusions at the end of GDA on the acceptability of:
• The types of waste and spent fuel
• The plans for conditioning of…
6) INDUSTRIAL COMPLEMENTARITIES BETWEEN INTERIM STORAGE AND
REVERSIBLE GEOLOGICAL REPOSITORY (wP-59237)
Jean-Michel Hoorelbeke, Andra (France)
The French Act voted in 2006 made the choice of deep geological disposal as the reference option for ILW and HLW long term
management. The CIGEO repository project aims at avoiding or limiting burden to future generations, which could not be achieved
by the extension in time of interim storage. The reversibility as provided by the Act will maintain a liberty of choice for waste management
on a duration which is comparable to new storage facility.
Interim storage is required to accommodate waste as long as the repository is not available. The commissioning of the repository
in 2025 will not suppress needs for interim storage. The paper describes the complementarities between existing and future
interim storage facilities and the repository project: repository operational issues and planning, HLW thermal decay, support for the
reversibility, etc. It shows opportunities to prepare a global optimization of waste management including the utilization at best of
storage capacities and the planning of waste emplacement in the repository in such a way to facilitate operational conditions and
to limit cost. Preliminary simulations of storage-disposal scenarios are presented.
Thanks to an optimal use of the waste management system, provision can be made for a progressive increase of…
7) RECENT DEVELOPMENTS IN SPENT FUEL MANAGEMENT IN NORWAY (wP-59260)
Peter Bennett, Barbara Oberlander, Erlend Larsen, Institutt for Energiteknikk (Norway
Spent Nuclear Fuel (SNF) in Norway has arisen from irradiation of fuel in the NORA, Jeep I and Jeep II reactors at Kjeller,
and in the Heavy Boiling Water Reactor (HBWR) in Halden. In total there is some 16 tonnes of SNF, with 12 tonnes of aluminium-clad
fuel, of which 10 tonnes is metallic uranium fuel and the remainder oxide (UO2). The portion of this fuel that is similar to
commercial fuel (UO2 clad in Zircaloy) may be suitable for direct disposal on the Swedish model or in other repository designs.
However, metallic uranium and/or fuels clad in aluminium are chemically reactive and there would be risks associated with direct
disposal.
Two committees were established by the Government of Norway in January 2009 to make recommendations for the interim
storage and final disposal of spent fuel in Norway. The Technical Committee on Storage and Disposal of Metallic Uranium Fuel
and Al-clad Fuels was formed with the mandate to recommend treatment (i.e. conditioning) options for metallic uranium fuel and
aluminium-clad fuel to render them stable for long term storage and disposal. This committee, whose members were drawn from
the nuclear industry, reported in January 2010, and recommended commercial reprocessing as the
8) ADVANCED SURVEILLANCE TECHNOLOGIES FOR USED FUEL
LONG-TERM STORAGE AND TRANSPORTATION (wP-59032)
Hanchung Tsai, Yung Liu, Mark Nutt, Argonne National Laboratory; James Shuler, US Department of Energy (USA)
Dry cask storage systems are being used by utilities in the United States to handle the ever-increasing number of discharged
fuel assemblies from nuclear power plants. Most of the newer systems incorporate multiple-purpose (storage, transport, and disposal)
or dual-purpose (storage and transport) canister technologies. With the prospect of very long-term storage (>120 years) and
deferred transport looming, condition- and performance-based aging management of structures and components in the dry cask
storage systems becomes an even more challenging task. From the standpoint of used fuels, one of the greatest concerns is embrittlement-related
cladding rupture of a large number of used fuel rods during long-term storage and transportation.
Radio frequency identification (RFID) is an automated and remote-sensing technology ideally suited to monitor sensitive assets
on a continuous, long-term basis. One such system, called ARG-US, has been developed by Argonne National Laboratory for the
U.S. Department of Energy Packaging Certification Program, Office of Packaging and Transportation, and deployed at several DOE
sites to track and monitor drums containing nuclear and radioactive materials. While the sensor suite currently in the ARG-US RFID
tags (seal, temperature, humidity, shock and radiation) is adequate in monitoring the exterior conditions of the used fuel casks,
advanced surveillance technology
73

Session 14 Abstracts
SESSION 14 — D&D OF POWER REACTORS AND RESEARCH REACTORS (3.9)
1) DFD AN APPROACH TO NEW REACTOR DESIGNS (wP-59197)
Jas S. Devgun, Sargent & Lundy (USA)
Design for Decommissioning (DfD) is now becoming a part of the design optimization process for the new reactor designs.
This is a significant contrast to when the currently operating reactors were designed several decades ago and when decommissioning
was not given much thought during the design process. At a time when nuclear renaissance has taken hold worldwide and many
reactors are in the planning or early construction stages, design considerations for decommissioning will have a significant impact
not only during the construction but also during the eventual decommissioning phase albeit long after the design stage as most reactors
are now designed for 60 year operating life.
Industry has taken a lead in this area and all current designs incorporate decommissioning considerations into the designs of
the new reactors to some degree. Some, such as, AP1000 are highly optimized in this regard. The goals are to have fewer components,
provide for modular designs for construction and eventual deconstruction, address major component removal issues, minimize
the generation of radioactive waste, and provide for better radiological safety.
International interest in the area has culminated in new or updated guidance on the subject at the IAEA and NEA. The IAEA
has drafted a technical…
2) FEEDBACK FROM WESTINGHOUSE EXPERIENCE ON SEGMENTATION
OF REACTOR VESSEL INTERNALS (wP-59013)
Joseph Boucau, Westinghouse Electric Company; Stefan Fallström, Westinghouse;
Per Segerud, Westinghouse Electric Sweden; Paul Kreitman, Westinghouse Electric Company (Belgium/Sweden/USA)
With more than 20 years of experience in the development of reactor vessel internals segmentation and packaging technology,
Westinghouse has accumulated significant know-how in the reactor dismantling market.
Building on tooling concepts and cutting methodologies developed decades ago for the successful removal of nuclear fuel from
the damaged Three Mile Island Unit 2 reactor (TMI-2), Westinghouse has continuously improved its approach to internals segmentation
and packaging by incorporating lessons learned and best practices into each successive project.
Westinghouse has developed several concepts to dismantle reactor internals based on safe and reliable techniques, including
plasma arc cutting (PAC), abrasive waterjet cutting (AWJC), metal disintegration machining (MDM), or mechanical cutting. Westinghouse
has applied its technology to all types of reactors covering Pressurized Water Reactors (PWRs), Boiling Water Reactors
(BWRs), Gas Cooled Reactors (GCRs) and sodium reactors.
The primary challenges of a segmentation and packaging project are to separate the highly activated materials from the lessactivated
materials and package them into appropriate containers for disposal. Since space is almost always a limiting factor it is
therefore important to plan and optimize the available room in the segmentation areas.
The choice of the optimum cutting technology is important for a successful project implementation and…
3) UPDATE ON JOSE CABRERA NPP DECOMMISSIONING (wP-59322)
Juan Santiago, Nieves Martin, Manuel Rodriguez, ENRESA (Spain)
Construction of José Cabrera Nuclear Power Plant, owned by Gas Natural, began in 1964 and the plant went into commercial
operation in 1969. The nuclear steam supply system was designed and supplied by Westinghouse and is made up of a light PWR
reactor with an authorized thermal output of 510 MW and an electrical power of 160 MW and all the auxiliary and safety systems
required for the efficient operation of the facility under safe conditions.
In 2002, the Ministry of Economy authorized the operation of the plant until April 30th 2006. Subsequently, the Directorate
General for Energy Policy and Mines, through of Order of April 20th 2006, confirmed the definitive shutdown of the plant on the
schedule date and established the requirements to be met in performing activities at the facility prior to awarding of the dismantling
permit, along with the basic framework for the granting of this authorization.
On April 30th 2008, ENRESA requested the transfer of the ownership of the José Cabrera NPP from the Ministry of Industry,
Tourism and Trade, along with the corresponding authorization for performance of the Dismantling and decommissioning Plan,
submitting the documentation required by article 30 of the Regulation on Nuclear and…
4) THE DECOMMISSIONING OF THE CIEMAT NUCLEAR RESEARCH CENTRE (w/oP-59321)
Juan Santiago, Sergio Vidaechea, Manuel Ondaro, ENRESA (Spain)
CIEMAT, formerly the Nuclear Energy Board (JEN), is the Spanish Centre for Energy-Related, Environmental and Technological
Research. Located in Madrid, it used to have more than 60 facilities in operation that allowed a wide range of activities in the
nuclear field and in the application of ionising radiations. Particularly significant among these facilities were the research reactors,
particle accelerators, hot cells and nuclear fuel manufacturing and processing plants.
At present the centre, which is authorised as a single nuclear facility, includes various installations, some of them are now obsolete,
shut down and in dismantling phases. In 2000 CIEMAT started the Integrated plan for the improvement of CIEMAT installations
(PIMIC), which includes activities for the decontamination, dismantling and rehabilitation of obsolete facilities.
The PIMIC-Decommissioning Project, carried out by ENRESA as main contractor, includes the dismantling of 4 installations:
JEN-1 Research Reactor, Reprocessing plant (Hot Cell M-1), Radioactive Liquid Treatment Plant and Radioactive Liquid Storage
Plant. Besides, a small contaminated area has to be remediated and restored, because of an incidental leakage of radioactive liquid
in the 70´s.
Currently, decommissioning activities in buildings have been completed, and soil remediation is under way together with the
final radiological characterisation of the soil, including…
74

Abstracts Session 14
5) THE REMOVAL, TRANSPORTATION AND FINAL TREATMENT AND CONDITIONING
OF THE THETIS RESEARCH REACTOR SPENT FUEL OF THE UNIVERSITY
OF GHENT (BELGIUM) ACHIEVED IN 2010 AUTHORS (wP-59261)
Hubert Thierens, Myriam Monsieurs, Ghent University; Vincent De pooter, Marnix Braeckeveldt, NIRAS/ONDRAF;
Luc Noynaert, SCK●CEN; Patrick Lewandowski, Belgoprocess; Patrick Maris, Luc Ooms, SCK●CEN; Karel Strijckmans, Ghent University (Belgium)
The THETIS research reactor on the site of the Nuclear Sciences Institute of the Ghent University has been in operation from
1967 until December 2003. This light-water moderated graphite-reflected low-enriched uranium pool-type reactor has been used
for various purposes e.g. the production of radio-isotopes and activation analyses. During the first years its core power was 15 kW.
In the early 70, a core enlargement allowed for operation at typically 150 kW, while the maximum was allowed to be 250 kW. The
fuel was 5% enriched uranium cladded with AISI304L stainless steel, with graphite plugs at both end of the tubes.
In order to decommission the reactor, the spent fuel and other nuclear materials present had to be removed from the reactor
site.
Ghent University entrusted to SCK”CEN, the Belgian Nuclear Research Centre , the study of the further management of the
spent fuel. Various options such as reprocessing, intermediate storage awaiting final disposal were investigated. However the characteristics
and the small amount of spent fuel made these solutions very expensive. In the meantime NIRAS/ONDRAF, the Belgian
radioactive waste management agency, was developing together with Belgoprocess, a solution for final conditioning in 400
liter drums and further intermediate storage of the…
6) DECOMMISSIONING AND DISMANTLING OF THE FRENCH BRENNILIS NPP (w/oP-59366)
Thierry Andre, ONET Technologies; Werner Botzem, Nukem Technologies (France/Germany)
This paper deals with the dismantling of the Brennilis NPP plant located in the west of France (Finistère). This prototype NPP
of Brennilis was the unique reactor of the heavy water developed in France during the 50 and the 60. The reactor diverged in
December 1966 and the NPP was operated during 9 years from 1972 to 1981, then the permanent shutdown occurred in July 1985.
In 2008, the operator and owner of the plant Electricité de France (EDF) commissioned consortium Onet Technologies (France)
and Nukem Technologies (Germany) with the dismantling of the reactor block of the NPP.
The reactor block essentially contains the reactor vessel including built-in units and biological shields, the peripheral piping as
well as systems for controlling the nuclear-related process. In addition to the complete dismantling, the scope of the contractual
services also includes their proper handling in accordance with the applicable regulation : safety requirements, waste management,
radioprotection optimization and management.
The central element of the plant is the reactor pressure vessel filled with heavy water. Each of the 216 horizontal fuel element
channels made of zircaloy is at each side connected to a pipe which directs the heat transfer gas to a header mounted…
7) THE CHOOZ A REACTOR DISMANTLING PROJECT (wP-59363)
Estelle Grevin, EDF; Joseph Boucau, Westinghouse Electric Company (France/Belgium)
Located in the Ardennes next to the Meuse River, Chooz A nuclear power plant was the first Pressurised Water Reactor (PWR)
built in France (1963). Its a 305 MW NPP and it produced electricity from 1967 until 1991 (38TWh). Chooz A NPP was permanently
shut down in 1993 and the fuel was removed.
The complete dismantling decree was published in September 2007. According to this decree, the dismantling is spilt into 3
main steps :
1st step: dismantling of all the nuclear equipment (2008 to 2015)
2nd step: tritium ratio decrease monitoring.(2015-2017)
3rd step: dismantling of the equipment needed for gathering. Filling of the underground buildings with concrete.
In 2010 the dismantling of the circuits connected to the vessel commenced. On Monday, the 1st of February, the first steam
generator was extracted and prepared to be decontaminated. Steam generators and the primary circuit will be decontaminated before
being transported in one piece to the French nuclear waste storage facility.
Once the decontamination is complete, the vessel dismantling will begin: this will be another important step for the project.
8) FULL SYSTEM DECONTAMINATION (FSD) PRIOR TO DECOMMISSIONING (wP-59189)
Christoph Stiepani, AREVA NP GmbH (Germany)
Decontamination prior to decommissioning and dismantling is imperative. Not only does it provide for minimization of personnel
dose exposure but also maximization of the material volume available for free release. Since easier dismantling techniques
in lower dose areas can be applied, the licensing process is facilitated and the scheduling and budgeting effort is more reliable.
The most internationally accepted approach for decontamination prior to decommissioning projects is the Full System Decontamination
(FSD). FSD is defined as the chemical decontamination of the primary cooling circuit, in conjunction with the main auxiliary
systems.
AREVA has long-term experience with Full System Decontamination for return to service of operating nuclear power plants
as well as for decommissioning after shutdown. Since 1976, AREVA has performed over 500 decontamination applications and
from 1986 on, decontaminations prior to decommissioning projects which comprise virtually all nuclear power plant (NPP) designs
and plant conditions:
• NPP designs: HPWR, PWR, and BWR by AREVA, Westinghouse, ABB and GE
• Decontaminations performed shortly after final shutdown or several years later, and even after re-opening safe enclosure
• High alpha inventory and or low gamma/alpha ratio
• Main coolant chemistry (e.g. with and without Zn injection during operation)
Fifteen decontaminations prior to…
75

Session 15 Abstracts
SESSION 15— THE FRENCH D&D ACTIVITIES - ORGANIZATION, STRATEGY,
OBJECTIVES AND EXPERIENCE (3.2)
1) CEA’S DECOMMISSIONING POLICY AND STRATEGIES. LESSONS LEARNED (w/oP-59203)
Philippe Guiberteau, Didier Dall’ava, CEA; Jean-Guy Nokhamzon, CEA/DEN/DADN (France)
Since the beginning of the 20th century, France has carried out research programmes on civil use of nuclear, and its application,
France has set up and run various types of installations: research or prototypes reactors, process study or examination laboratories,
pilot installations, accelerators, nuclear power plants and processing facilities. There are currently more than several tens of
facilities which are presently closed down pending dismantling or in the process of being dismantled by CEA , the governmental
body for research and development in nuclear and renewable energies..
When operating, all these installations work with nuclear materials and generate radioactive waste. When they are shutdown,
either as a result of the programmes for which they were set up, or due to equipment wearing out or being obsolete, these installations
must be cleaned and dismantled, taking into account their nuclear nature and requirements related to safety and environment.
During the decommissioning process, the implementer has to deal with safety and site rehabilitation issues.
Dealing with these installations is a long-term programme which must be carefully planned and financed in order to optimise
its management.
The paper will describe the French decommissioning policy and strategies adopted, showing that :
• Safety is guaranteed…
2) CLEANSING AND DISMANTLING OF CEA-SACLAY NUCLEAR LICENSED FACILITIES (W/OP -59227)
Michel K. Jeanjacques, Rebecca Glévarec, Isabelle Delaire,
Jean Louis Martin, Commissariat à l’Energie Atomique et aux Energies Alternatives (France)
This summary presents the cleansing and dismantling operations currently realized on the CEA center of Saclay (CEA-Saclay).
This CEA center was created at the beginning of the Fifties on the plateau of Saclay located at approximately 25 km at the south
of Paris. The CEA-Saclay as of its creation was dedicated to fundamental research, the studies for the development of the nuclear
dies, the uranium enrichment and the radioelement study and production.
The Saclay-center nuclear facilities were already dismantled in function of the end of R&D and fundamental research (research
reactor: EL2-EL3, critical mock-up, uranium enrichment pilot plants, radioelement production cells, and accelerators SATURNE-
ALS [Saclay Linear Accelerator]). It was initiated at the beginning of the 2000 years a cleansing and dismantling program of the
old Nuclear Licensed Facilities (LNF). 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).
The LHA are a multipurpose laboratory for R&D studies of various units of the CEA-Saclay. They were built at the end of the
Fifties. The reference safety frame allowed disassembling the equipment at the end of R&D program. Since the beginning…
3) DECONTAMINATION AND DISMANTLING OF CENDRILLON TRANSFER
SYSTEMS FOR RADIOACTIVE LIQUID SOLUTIONS (w/oP -59336)
Michel K. Jeanjacques, Commissariat à l’Energie Atomique et aux Energies Alternatives;
Frédéric Masure, Alternative Energies and Atomic Energy Commission (France)
The CENDRILLON system was studied and developed by the CEA at the end of the 1950s and early of the 1960s to transfer
and transport the radioactive liquid solutions to waste treatment facilities. This system has been manufactured in several versions
in three different sizes and for each different volumes of capacity. For each size, the biological shielding thickness is based on the
volume capacity. Whatever the size and volume, the CENDRILLON connection system remains identical. All liquid transfers, filling
and sucking out, of the CENDRILLON are carried under vacuum.
The CENDRILLON D&D works are carried out during the facilities POCO (post clean out operations) and decommissioning
or into a dedicated waste treatment plant.
The parer will show CEAs procedure to carry out these CENDRILLON D&D works. It consists of tasks sequences: CEN-
DRILLON emptiness assessment, capacity flushing and decontamination, pumping out, drying and finally CENDRILLON dismantling
by mechanical disassembly (taking apart) and the capacity cutting. Control of nuclear risk is essential for all these tasks: radiolysis,
contamination and irradiation.
4) AREVA RETURN ON EXPERIENCE FROM D&D PROGRAMME MANAGEMENT -
WHAT WE HAVE LEARNED SO FAR? (w/oP -59324)
Jean-Michel Chabeuf, Thierry Varet, Grégoire de Laval, Guy Decobert,
Frédéric Chambon, AREVA Nuclear Site Value Development BU (France)
In November 1997, UP1, France first large scale reprocessing plant, ceased operations after 40 years of activities. A comprehensive
D&D program was immediately initiated, scheduled to last for a period of approximately 30 years. In 2002, AREVA
launched the decommissioning and dismantling of SICN sites, two GCR fuel fabrication located near Grenoble and Annecy. Shortly
after, in 2003, the second reprocessing plant, UP2 400, commissioned in the sixties in La Hague (Normandy) followed. Less than
a decade later, UP1 decommissioning program is well advanced, with the de-cladding facilities nearing completion, and the chemical
plant showing a work progress of about 50%. The decommissioning of SICN sites is reaching its final stage, with concrete
scrabbling operations launched in order to release the site for non nuclear industrial activities. A part of UP2 400 de-cladding facilities
have been dismantled, and a vast D&D program is now on track for the bulk of the plant.
AREVA is managing those operations, either as owner in La Hague and SICN, or as prime contractor for the French Atomic
Energy commission in Marcoule.
More than 10 years of continuous, large scale D&D operations have provided a unique feed back for such operations.
RETURN ON EXPERIENCE OF…
76

Abstracts Session 16
SESSION 16 — NATIONAL AND INTERNATIONAL D&D PROGRAMS (3.3)
1) PARTICULARITIES OF CHNPP SITE REMEDIATION DURING ITS DECOMMISSIONING (wP-59193)
Sergii Mitichkin, Valeriy Seyda, Chernobyl NPP (Ukraine)
On April 26, 1986 beyond designed accident occurred at Chernobyl NPPs Unit 4 as a result of which the reactor core and protective
safety barriers have been destroyed. Releases of fission products are evaluated approximately in 50 MKu (without considering
inert radioactive gases) that makes approximately 3,5 % of total quantity of the radio nuclides accumulated in the reactor as
of the moment of accident.
To liquidate the accident consequences it has been constructed the Shelter object. The major part of fission nuclear materials
is localized within the Shelter object in the form of separate elements of fuel assemblies and congestions of Fuel Containing Materials.
The de?ontamination works carried out in 1986, have allowed to clean up ChNPP site from a main part of radioactive substances.
That has provided a possibility to operate ChNPP site equipment without the excess of a dose limit established in normative
documents. But a significant amount of reactor core fragments (according to some estimations - from 500 kg up to 1000 kg)
remains at ChNPP territory under a concrete and ground layer, laid in 1986 with the purpose to reduce radiation conditions parameters
at the site up to the normative documents requirements. The given circumstance
2) DIVISION OF NUCLEAR LIABILITIES BETWEEN DIFFERENT LICENSE HOLDERS AND OWNERS (wP-59214)
Staffan Lindskog, Swedísh Radiation Safety Authority; Rolf Sjöblom, Tekedo AB (Sweden)
Operation of nuclear facilities typically implies that substantial liabilities for decommissioning and waste management are
incurred. In the case of Sweden, and in accordance with the polluter pays principle, money is collected into segregated funds and
securities are provided to ensure that adequate funding will be available at the time when it is needed. For nuclear power plants,
the safeguarding of funds includes the estimated costs as well as an amount related to the risk that the Government takes as the ultimate
guardian of the system.
For other license holders, the fees and securities must include only the estimated cost. For old facilities, special problems may
arise since they might no longer generate any revenue. Another problem with old facilities is that it has been proven difficult, in
many cases, to obtain sufficiently precise cost calculations. There issues have been dealt with in previous presentations to the ICEM
by the present authors.
However, equally important - but so far largely neglected - is the issue of who is actually responsible for what. Of course, our
Environmental Code - as does the corresponding legislation in many other countries - states that the responsibility is a collective
one, and anyone involved can…
3) SPANISH APPROACH TO LARGE DECOMMISSIONING PROJECTS (wP-59320)
Juan Santiago, Alejandro Rodríguez, ENRESA (Spain)
Spain has accumulated significant experience in the field of decommissioning of nuclear and radioactive facilities. Relevant
projects include the decommissioning of research reactors and nuclear research facilities and the decommissioning of gas-graphite
and light water nuclear power plants. The decommissioning of nuclear facilities in Spain is undertaken by ENRESA, who is also
responsible for the management of radioactive wastes. The three most notable projects are the decommissioning of the Vandellós I
nuclear power plant, the decommissioning of the CIEMAT Nuclear Research Centre and the decommissioning of the José Cabrera
nuclear power plant.
The Vandellós I gas-graphite reactor was decommissioned in about five years (from 1998 to 2003) to what it is known as level
2. During this period, most plant systems and components were dismantled, the reactor vessel was confined and the facility was
prepared for latency. In 2005 the facility entered into a dormancy phase, with minimum operating requirements.
The decommissioning of the CIEMAT Research Center includes the dismantling of obsolete facilities, such as the research
reactor JEN-1, a pilot reprocessing plant, and a conditioning and storage liquid waste facility and the remediation of contaminated
soils. Dismantling works started in 2006 and have been completed by 2010.
In March…
4) DECOMMISSIONING OF OBSOLETE NUCLEAR FACILITIES IN THE
NUCLEAR RESEARCH INSTITUTE REZ (wP-59309)
Josef Podlaha, Karel Svoboda, Nuclear Research Institute Rez; Eduard Hanslik,
T.G.M. Water Research Institute (Czech Republic)
After more than 55 years of activities of the Nuclear Research Institute Rez (NRI) in the nuclear field, there are some obsolete
nuclear facilities that shall be decommissioned.
NRI is a leading institution in all areas of nuclear R&D in the Czech Republic. NRI has had a dominant position in the nuclear
programme since it was established in 1955 as a state-owned research organization and it has developed to its current status. In
December 1992, NRI has been transformed into a joint-stock company.
The Institute’s activity encompasses nuclear physics, chemistry, nuclear power, experiments at the research reactor and many
other topics. Main issues addressed in NRI in the past decades were concentrated on research, development and services provided
to the nuclear power plants operating VVER reactors, development of chemical technologies for fuel cycle and irradiation services
to research and development in the industrial sector, agriculture, food processing and medicine.
The NRI operates two research nuclear reactors, many facilities as a hot cell facility, research laboratories, technology for
radioactive waste (RAW) management, radionuclide irradiators, an electron accelerator, etc.
The obsolete facilities to be decommissioned comprise:
(1) Various research facilities
Hot cells used for research in the field of reprocessing of…
77

Session 17 Abstracts
SESSION 17 — APPLYING STRATEGIC PLANNING, DECISION-MAKING AND
RISK REDUCTION METHODOLOGIES IN EM (5.7)
1) CAN SUSTAINABILITY BE APPLIED TO OUR ENVIRONMENTAL
REMEDIATION CHALLENGES? (w/oP-59148)
Peter Booth, Vicky Gaskin, WSP Environment and Energy (UK)
There are many environmental remediation challenges around the world today with a radiological connotation. These in turn
relate to all aspects of the nuclear industry life cycle as well as the NORM industries and consequences of accidents /incidents.
In reality, apart from one or two major exceptions in a few counties who have extensive budgets allocated to environmental
remediation, we do not generally see a lot of real progress in the protection of human health and the environment from legacy issues.
It is important therefore to determine why this is the case and if there is anything that can be undertaken to improve the situation.
There are a number of reasons potentially leading to this lack of progress, namely;
• A lack of available funding;
• The diversion of funds to other issues deemed to be a greater priority;
• No practical experience in resolving such problems;
• Lack of established regulatory and/or procedural infrastructure.
More often than not when environmental remediation challenges exist, the decision makers only tend to look for final solutions.
If such final solutions cant be achieved, often because of funding restrictions, then little or no progress is generally made.
However, there is the potential through…
2) EVOLUTION OF PERFORMANCE ASSESSMENT MODELING IN THE US (w/oP- 59334)
Paul Black, John Tauxe, Neptune and Company, Inc. (USA)
Performance Assessment under DOE Orders and NRC regulations are evolving from the deterministic modeling that was performed
in the 1990s, to the probabilistic modeling that is being performed in current PA efforts. This evolution has also seen a change
from bottom-up process modeling to top-down system modeling, which is better suited for probabilistic modeling performed with
the goal of supporting decision analysis. This evolution is presented, with a description of how process modeling can be used effectively
to support system modeling, and how system modeling can be used effectively in a probabilistic environment to support PA
decisions such as disposal optimization, closure, and long-term management and maintenance. The decision analysis process implied
by this approach follows the basic tenets of Bayesian methods, the scientific method, and DOE’s as low as reasonably achievable
process, and allows DOE’s performance assessment maintenance program to become operational and measurable. Technical nuances
in this type of PA modeling such as uncertainty and sensitivity analysis methods that can be applied to such complex, dynamic, nonlinear,
non-monotonic models, and issues associated with proper model scaling are also presented. Specific examples are presented
from performance assessment modeling conducted at several radioactive waste disposal facilities in the US.
SESSION 18 — ECONOMIC ANALYSES, MONITORING STRATEGIES AND PROJECT
MANAGEMENT IN ENVIRONMENTAL MANAGEMENT (5.6)
1) DELIVERING VALUE FOR MONEY - TRUST AND VERIFY? (wP-59253)
Alastair Laird, Project Time & Cost Inc. (USA)
Accurate estimates for national Environmental Management remediation work programmes are an essential ingredient of
ensuring that plans can be adequately funded. They also form the basis of value measurement as the work is executed on an annual
or programme basis. However, the inherent uncertainties of many of the EM and decommissioning tasks, both in terms of the
technical challenges faced, options available, end states to be achieved; and the general risks and uncertainties associated with the
hazard and its characterisation means that many estimates were always going to be subject of very high levels of uncertainty.
In 2002 the United Kingdom Nuclear Liabilities Estimate was quoted as £48Bn when the government restructured the UK civil
nuclear industry and set out the basis for forming what was to become the Nuclear Decommissioning Authority (NDA). By 2005
the NDA had assessed the costs as £56Bn but by 2008 the costs had significantly increased to £73Bn and continue to rise. How
does this relate to the more immediate challenges of working off the plan and demonstrating Value for Money can be achieved in
the near term? In parallel the US Department of Energy EM Office introduced its best-in-class initiative in 2007 – the…
2) THE TECHNICAL AND ECONOMICAL OPTIMIZATION OF THE
FRENCH GEOLOGICAL REPOSITORY PROJECT (w/oP-59275)
Rodolphe Raffard, Thibaud Labalette, Andra (France)
The French Act of 28 June 2006 made the choice of reversible geological repository for long term management of high level
and long-lived intermediate level waste. Andra is in charge of designing, building and operating the future industrial repository
Cigéo. Current major issues consist in preparing the application to be examined in 2015, planning the construction so that operation
would start in 2025 and optimizing the design on both technical and economical points of view.
The Dossier 2005 -provided by Andra prior to the 2006 Act- established the feasibility of the project, especially towards compliance
with safety and reversibility. Design options were presented at that time with the objective of demonstrating feasibility without
ruling out possibilities of further optimization.
Along with the scientific and technical review of Dossier 2005, a number of design optimization topics were identified in 2006.
Working groups involved Andras specialists as well as external experts. A particular attention was given to (i) the industrial experience
of waste producers and (ii) the characteristics of the clay layer investigated in the Meuse/Haute-Marne Underground
Research Laboratory.
The 2006 optimization topics were prioritized taking into account their economical impact and the development plan of the
project. They have been implemented…
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Abstracts Session 19
3) THE ENVIRONMENTAL MONITORING SYSTEM DEVELOPED WITHIN THE FRAMEWORK
OF THE FRENCH RADIOACTIVE WASTE DEEP REPOSITORY PROJECT (w/oP-59296)
Elisabeth Leclerc; Patrick Landais, Andra (France)
In 2007, an environmental monitoring system, called the Observatoire Pérenne de lEnvironnement (OPE) was launched by
Andra in order to establish the environmental initial state and to monitor ecosystems around the Meuse/Haute-Marne region (East
of France), before the potential installation of a national deep repository of radioactive waste. The OPE aims to characterize an area
covering 900 hundreds of kilometres and to follow environmental evolutions during exploitation, i.e. over 100 years.
The OPE is associated to a comprehensive research and development program involving the deployment of important scientific
tools covering all environmental compartments since several years. The objectives are:
• to gather and analyse physical, chemical, biological and radiological data on the initial state of the environment including
samples preservation from different areas (air, water, forest wildlife and flora, soils, agricultural food chain, etc.)
• to assess the very long term evolution of the environmental quality;
• to model elements biogeochemical cycles, mass and energy fluxes and to study interactions of processes between environmental
areas;
• to anticipate impacts from anthropogenic pressures (industrial, agricultural, climatic, on a local or global scale);
• to study links between environment and human health.
The OPE is currently developing large-scale scientific tools and collecting…
SESSION 19 — POSTER SESSION: SPENT FUEL, FISSILE, TRANSURANIC
AND HIGH LEVEL WASTE MANAGEMENT (2.1)
1) ADONIS, HIGH COUNT RATE HP-GE Ƴ SPECTROMETRY ALGORITHM:
IRRADIATED FUEL ASSEMBLY MEASUREMENT (wP-59234)
Patrick Pin, AREVA NC; Eric Barat, Thomas Dautremer, Thierry Montagu, Stéphane Normand, CEA - Saclay (France)
ADONIS is a digital system for gamma-ray spectrometry, developed by CEA. This system achieves high count-rate gammaray
spectrometry with correct dynamic dead-time correction, up to, at least, more than an incoming count rate of 3:106 events per second.
An application of such a system at AREVA NC’s La Hague plant is the irradiated fuel scanning facility before reprocessing.
The ADONIS system is presented, then the measurement set-up and, last, the measurement results with reference measurements.
2) TECHNICAL KNOW-HOW FOR THE INVESTIGATION AND MODELLING OF
TOPOGRAPHIC EVOLUTION FOR SITE CHARACTERISATION (wP-59171)
Ryosuke Doke, Ken-ichi Yasue, Tadafumi Niizato, Akio Nakayasu, Japan Atomic Energy Agency (Japan)
Geological hazard assessments are being used to make important decisions relevant to the constructing nuclear facilities such
as repositories for deep geological disposal of high-level radioactive waste. With respect to such repositories, topographic evolution
is a key issue for description of the long-term evolution of a groundwater flow characteristics in time spans of tens to hundreds
of thousands of years. The construction of topographic evolution model is complex, involving tacit knowledge and working
processes. Therefore, it is important to externalise, that is to explicitly present the tacit knowledge and decision-making processes
used by experts in the model building unambiguously, with thorough documentation and to provide key knowledge to support planning
and implementation of investigations.
In this study, documentation of the technical know-how used for the construction of a topographic evolution model is demonstrated.
The process followed in the construction of the model is illustrated using task-flow logic diagrams; the process involves
four main tasks with several subtasks. The task-flow for an investigation to estimate uplift rates is also illustrated linked to the taskflow
for the modelling of topographic evolution. In addition, the decision-making processes in the investigation are expressed in
logical IF-THEN format for each task. Based on the documented…
3) VALIDATION OF CORRELATIONS BETWEEN ND ISOTOPES AND DIFFICULT-TO-MEASURE NUCLIDES
PREDICTED WITH BURN-UP CALCULATION CODE BY POST IRRADIATION EXAMINATION (wP-59086)
Shiho Asai, Keisuke Okumura, Yukiko Hanzawa, Hideya Suzuki, Masaaki Toshimitsu, Jun Inagawa, Takaumi Kimura,
Japan Atomic Energy Agency; Satoru Kaneko, Kensuke Suzuki, Tokyo Electric Power Company (Japan)
Correlations between Nd isotopes and difficult-to-measure (DTM) nuclides, such as Se-79, Tc-99, Sn-126, and Cs-135, predicted
using a calculation code have been validated by postirradiation examination (PIE). The calculation was performed with a
burnup calculation code, MVP-BURN, using the updated nuclear data library JENDL-4.0. An irradiated PWR fuel with a burnup
of 44.9 GWd/t and a cooling time of 7458 days was used as a standard sample. The concentrations of Nd isotopes in the sample
solutions were determined by inductively coupled plasma mass spectrometry (ICP-MS) after purification by two consecutive anionexchange
separations. The ratios of Se-79 and Cs-135 to Nd isotopes (Nd-145, Nd-146, and Nd-145+Nd-146) calculated using
MVP-BURN were in good agreement with PIE values within the deviations of 8% and 6%, respectively. This indicates that these
calculated ratios are applicable to the scaling factors of Se-79 and Cs-135. For Tc-99 and Sn-126, the calculated values were respectively
about 50% and 20% higher than the PIE values. These overestimations were mainly caused by the lack of the contribution
of an insoluble residue to the measured concentrations.
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Session 19 Abstracts
4) COMPUTATIONAL STUDY FOR INVENTORY ESTIMATION OF SE-79, TC-99, SN-126, AND CS-135 IN HIGH-
LEVEL RADIOACTIVE WASTES FROM SPENT NUCLEAR FUELS OF LIGHT WATER REACTORS (wP-59087)
Keisuke Okumura, Shiho Asai, Yukiko Hanzawa, Tsutomu Okamoto, Hideya Suzuki, Masaaki Toshimitsu,
Jun Inagawa, Takaumi Kimura, Japan Atomic Energy Agency; Satoru Kaneko,
Kensuke Suzuki, Tokyo Electric Power Company (Japan)
Inventory estimation of long-lived fission products (LLFPs) in high-level radioactive wastes (HLW) from spent nuclear fuels
of light water reactors is important for a safety assessment of their disposal. In order to develop an inventory estimation method of
difficult-to-measure LLFPs (Se-79, Tc-99, Sn-126, and Cs-135), a parametric study was carried out by using a sophisticated burnup
calculation code and data. In the parametric study, fuel specifications and irradiation conditions are changed in the conceivable
range. The considered parameters are fuel assembly types (PWR / BWR), U-235 enrichment, moderator temperature, void fraction,
power density, and so on. From the calculated results, we clarify the burnup characteristics of the target LLFPs and their possible
ranges of generations. Finally, candidates of the key nuclide are proposed for the scaling factor method of HLW.
5) INDUSTRIAL SCALE HL-LL WASTE CANISTER TRANSFER DEMONSTRATOR (wP-59305)
Pascal Champ, Jacques Bardet, Benjamin Attias, Cegelec (France)
In 2007, Cegelec has been attributed a contract by ANDRA under the ESDRED program (Engineering Studies and Demonstrations
of Repository Designs) financed by 13 organisations across Europe, for the design, manufacturing and trial test of a full scale
industrial demonstrator of HL-LL waste canister transfer system.
Completed in 2009, this project gives a good synthesis of solutions the industry can offer in order to manage HLW transportation
with regard to deep geological disposal.
This paper highlights solutions developed and results achieved with numerous pictures of the actual system.
6) CESAR5.3: AN INDUSTRIAL TOOL FOR IRRADIATED NUCLEAR FUEL
AND WASTE CHARACTERISATION, WITH AN ASSOCIATED QUALIFICATION (w/oP-59080)
Jean-Marc Vidal, Romain Eschbach, Commissariat à lÉnergie Atomique et aux Énergies Alternatives;
Agnes Launay, Christophe Binet, AREVA_NC (France)
CESAR (Simplified Evolution Code Applied to Reprocessing) is a depletion code developed between CEA and AREVA. This
code was first used in the La Hague reprocessing plant Laboratories in 1980, to confirm the nuclear data experimental measurements.
The use of the CESAR code was then extended to the characterizations of various type of irradiated nuclear fuel (PWR/UOx
URE and MOx ; BWR/UOx and MOx ; MTR and Fast Reactors) and the associated produced waste. The code can distinguish more
than 100 heavy nuclides, 200 fission products and 150 activation products (in particular Tritium and Helium generation are included).
Both the fuel and its structural materials can be characterized. The CESAR code can also perform depletion calculations from
3 months to 1 million years of cooling time.
The updated version of the code is related to the harmonization between nuclear data and calculation schemes (APOLLO2)
based on the JEFF3.1.1 nuclear data library. The current features allow fast characterizations for both irradiated fuel and waste, calculating:
material balance, activity, decay heat, neutron source and spectrum, radiotoxicity source, gamma and alpha source and
their respective spectrum. The CESAR code can also calculate the coefficients used in nuclear material transport and in classification
of…
7) TEST PROCEDURE WITH A 15,000 KG HALF-SCALE PROTOTYPE
OF TRANSPORT AND STORAGE CASK (w/oP-59141)
Andre Musolff, Thomas Quercetti,
Karsten Müller, BAM - Federal Institute for Materials Research and Testing (Germany)
BAM is the competent authority for mechanical and thermal safety assessment of transport packages for spent fuel and high
level waste in Germany. In context with the package design approval procedure for transport and storage of new German cask several
drop test series were performed by BAM with a half-scale prototype.
The test program comprised a sequence of a total of 18 drop tests with different drop orientations, drop heights and temperatures.
The sequence of testing in the program consisted of a number of nine-meter free drop onto an unyielding target and several
drops from one meter onto a steel puncture bar. In order to cause maximum damage on the package various drop orientations were
performed according to the most severe drop position as well as most sensitive parts of the container.
The subsequent release of radioactive substances must not exceed a value specified in the dangerous goods transport regulations.
Radiation shielding and nuclear safety has to be guaranteed. The prototype was tested under normal and accident conditions
of transport in the 200 tons BAM drop test facility at BAM Test Site Technical Safety.
Extensive test methods as well as comprehensive measurement data are presented within the complexity of performed drop test
procedures.
8) CAPILLARY ELECTROPHORESIS WITH LASER-INDUCED FLUORESCENT DETECTION METHOD USING
HIGHLY EMISSIVE PROBES FOR ANALYSIS OF ACTINIDES IN RADIOACTIVE WASTES (wP-59092)
Tomoko Haraga, Japan Atomic Energy Agency; Yuta Nakano, Masami Shibukawa, Saitama University; Yutaka Kameo,
Kuniaki Takahashi, Japan Atomic Energy Agency; Shingo Saito, Saitama University (Japan)
For the safe disposal of radioactive wastes, it is indispensable to evaluate radioactivity concentration in each waste package.
Actinides are important nuclides for the safety analysis of radioactive wastes from nuclear fuel cycle facilities. In order to analyze
many kinds of waste samples, a simple, fast and highly sensitive analytical method for actinides is required. While capillary electrophoresis
(CE) has been employed for the analysis of ionic species including actinide ions with advantage of the high separation
efficiency and simpleness so far, there is no report for CE method providing high sensitivity amenable to practical use, to our
knowledge. In this study, an approach to develop new emissive probes for actinide ions using CE-laser-induced fluorescent detection
(LIF) was made for the first time. The separation and detection of neptunium (Np-237) and americium (Am-243) was exam-
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Abstracts Session 19
ined as a model nuclide using several new emissive complexing probes, each of which possesses a fluorophore (fluorescein) and a
different chelating moiety (hexa-octadentate, and acyclic or macrocyclic polyaminocarboxylate). Applying the actinide-probe complexes
to a pre-capillary complexation technique, in which an emissive probe was mixed to a sample solution before electrophoresis
without addition of the emissive probe to the carrier electrolyte, the highly sensitive fluorescent detection…
9) A NEW WAY OF ELIMINATING TRIBUTYLPHOSPHATE AND DODECANE MIXTURES
USING ADVANCED OXIDATION TECHNIQUES (w/oP-59104)
Geraldine Dupuy, DEWDROPS (France)
Tributylphosphate (TBP)/dodecane mixtures are widely used as extraction solvents in the PUREX process. The process is well
known as an efficient method for Uranium and Plutonium recovery from spent nuclear fuel. After undergoing several cycles, the
performance of the PUREX process is impaired by chemical and radiolytic damage to the TBP and dodecane molecules. The used
extraction solvent becomes an organic nuclear waste for which disposal options are scarce. Currently, the dodecane can be recycled
or incinerated after TBP removal to limit corrosion problems. However, the separation of the two solvents still leaves untreated
extraction products that accumulate awaiting a satisfactory disposal solution.
Dewdrops has developed and optimized a treatment based on advanced oxidation techniques that provides an elegant and costeffective
solution particularly well adapted to small arisings of complex mixtures originating from the PUREX process. The organic
waste is completely mineralized yielding only effluents for which disposal routes are already available. The patented oxidation
process uses the combination of hydrogen peroxide and UV-C radiation with or without a catalyst to produce hydroxyl radicals
capable of mineralizing organic matter to carbon dioxide and water. The performance of the process has been proven in an experimental
set up comprising a 14…
10) THE FP7 COLLABORATIVE PROJECT RECOSY (w/oP-59397)
Gunnar Buckau, Institute for Transuranium Elements, Joint Research Center, European Union;
Anne Delos, Vanessa Montoya, Amphos 21 (Germany/France/Spain)
The Collaborative Project REdox phenomena Controlling SYstems (RECOSY) started in 2008 falls within the EURATOM
program and is implemented within the 7th Framework Program.
The main objective of ReCosy is the sound understanding of redox phenomena controlling the long-term release/retention of
radionuclides in nuclear waste disposal providing tools to apply the results to Performance Assessment/Safety Case.
Although redox is not a new issue, different questions are still not resolved, such as, redox processes in the long-term dissolution/chemical
transformation of the radioactive waste, waste packages and engineered barriers, and migration in the far-field,
including which species are formed and their respective various retention mechanisms. In order to solve this questions, the project
includes 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 to internal/external disturbances in disposal systems to internal/external disturbances.
The work program of the project is structured along six Research and Technological Development workpackages. Specific
workpackages on knowledge management, education and training (WP7) and administrative management issues (WP8) are also
included in the project. In WP1, the scientific state-of-the-art and its application to Performance Assessment/Safety Case is documented
and regularly up-dated, based on the safety case of the ANDRA B2 cell. WP2 deals with the development and testing of
redox determination methods using different type of electrodes as well…
11) TECHNICAL KNOW-HOW OF SITE DESCRIPTIVE MODELING FOR SITE CHARACTERIZATION (wP-59089)
Hiromitsu Saegusa, Tadafumi Niizato, Ken-ichi Yasue, Hironori Onoe,
Ryosuke Doke, Japan Atomic Energy Agency (Japan)
The site descriptive model covering the current status of characteristics of geological environment and the site evolution model
for estimation of the long-term evolution of site conditions are used to integrate multi-disciplinary investigation results. It is important
to evaluate uncertainties in the models, to specify issues regarding the uncertainties and to prioritize the resolution of specified
issues, for the planning of site characterization.
There is a large quantity of technical know-how in the modeling process. It is important to record the technical know-how with
transparency and traceability, since site characterization projects generally need long duration. The transfer of the technical knowhow
accumulated in the research and development (R&D) phase to the implementation phase is equally important.
The aim of this study is to support the planning of initial surface-based site characterizations based on the technical know-how
accumulated from the underground research laboratory projects. These projects are broad scientific studies of the deep geological
environment and provide a technical basis for the geological disposal of high-level radioactive wastes. In this study, a comprehensive
task flow from acquisition of existing data to planning of field investigations through the modeling has been specified. Specific
task flow and decision-making process to perform the tasks have been specified.
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Session 20 Abstracts
12) A COMPREHENSIVE INFORMATION MANAGEMENT SYSTEM FOR EUROPEAN DISPOSAL R&D
(INMAN): A PROPOSAL FOR THE NEXT EUROPEAN FRAMEWORK PROGRAM (w/oP-59397)
Gunnar Buckau, Institute for Transuranium Elements, Joint Research Center, European Union;
Anne Delos, Vanessa Montoya, Amphos 21 (Germany/France/Spain)
ABSTRACT NOT AVAILABLE
13) DEVELOPMENT OF COMPREHENSIVE TECHNIQUES FOR COASTAL SITE
CHARACTERIZATION: INTEGRATED PALAEOHYDROGEOLOGICAL APPROACH
FOR DEVELOPMENT OF SITE EVOLUTION MODELS (wP-59259)
Kenji Amano, Tadafumi Niizato, Kunio Ota, Japan Atomic Energy Agency; Bill Lanyon, Nagra;
W Russell Alexander, Bedrock Geosciences (Japan/Switzerland)
Radioactive waste repository designs consist of multiple safety barriers which include the waste form, the canister, the engineered
barriers and the geosphere. In many waste programmes, it is considered that the three most important safety features provided
by the geosphere are mechanical stability, favourable geochemical conditions and low groundwater flux. To guarantee that a
repository site will provide such conditions for timescales of relevance to the safety assessment, any repository site characterisation
has to not only define whether these features will function appropriately today, but also to assess if they will remain adequate
up to several thousand to hundreds of thousand years into the future, depending on the repository type.
In general, this is done by studying the palaeohydrogeological evolution of a site, defining the temporal and spatial changes of
various properties and processes. These may include geology, hydrogeology, hydrochemistry and site tectonics, including uplift and
erosion processes. These key aspects are studied to build up a conceptual model for the overall site evolution over geological time,
up to the present and this is used to define the likely future evolution of the site and to assess if the main safety features will continue
to function adequately.
The collaborative programme…
SESSION 20 — PANEL: CHALLENGES WHEN SELECTING DISPOSAL OPTIONS IN THE LIGHT
OF THE NEW IAEA CLASSIFICATION SCHEME (1.17)
ABSTRACTS NOT REQUIRED
SESSION 21 — PANEL: CONTRIBUTION AND COMPLEMENTARITIES OF INTERIM STORAGE,
GEOLOGICAL DISPOSAL, PARTITIONING & TRANSMUTATION REVERSIBILITY REGARDING
GLOBAL OPTIMIZATION OF RADWASTE MANAGEMENT (2.15)
NEW NUCLEAR PROGRAMMES MUST NOT NEGLECT WASTE MANAGEMENT (wP-59077)
Charles McCombie, Arius Association (Switzerland)
Many established nuclear power programmes have learned to their dismay that waste management and disposal are not tasks
that can be postponed at will if public and political acceptance is a prerequisite for progress. In fact, some programmes that recognised
this back in the 1970s and 1980s moved into leading positions in repository development. This happened, for example, in
Sweden and Switzerland where already in the 1970s Laws were passed specifying that safe disposal must be demonstarted before
new nuclear plants could opersate. In recent years, it has become recognised that, in order to ensure that the radioactive wastes in
any country are managed safely, it is necessary to have an established legislative and regulatory framework and also to create the
necessary organizations for implementation and for oversight of waste management operations and facility development. Guidance
on these issues is given in the Joint Convention and a number of other IAEA documents. The IAEA, and also the EC, have in addition
published key overarching advisory documents for new nuclear programmes. These are useful for strategic planning but, when
it comes to actual implementation projects, the advice tends to imply that all nuclear programmes, however large or small, should
be pressing…
SESSION 22 — PANEL: CONTRIBUTION AND COMPLEMENTARITIES OF INTERIM STORAGE,
GEOLOGICAL DISPOSAL, PARTITIONING & TRANSMUTATION REVERSIBILITY REGARDING
GLOBAL OPTIMIZATION OF RADWASTE MANAGEMENT (2.15)
ABSTRACTS NOT REQUIRED
SESSION 23 — ADVANCED L/ILW CONDITIONING TECHNOLOGIES - PART 1 OF 2 (1.11)
1) CEMENTITIOUS MATERIALS FOR RADIOACTIVE WASTE MANAGEMENT
WITHIN IAEA COORDINATED RESEARCH PROJECT (wP-59021)
Zoran Drace, IAEA; Michael Ojovan, University of Sheffield (Austria/UK)
The IAEA Coordinated Research Project (CRP) on cementitious materials for radioactive waste management was launched in
2007. The objective of CRP was to investigate the behaviour and performance of cementitious materials used in radioactive waste
management system with various purposes and included waste packages, wasteforms and backfills as well as investigation of interactions
and interdependencies of these individual elements during long term storage and disposal. The specific research topics considered
were: (i) cementitious materials for radioactive waste packaging: including radioactive waste immobilization into a solid
waste form, (ii) waste backfilling and containers; (iii) emerging and alternative cementitious systems; (iv) physical-chemical
processes occurring during the hydration and ageing of cement matrices and their influence on the cement matrix quality; (v) methods
of production of cementitious materials for: immobilization into wasteform, backfills and containers; (vi) conditions envisaged
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Abstracts Session 24
in the disposal environment for packages (physical and chemical conditions, temperature variations, groundwater, radiation fields);
(vii) testing and non-destructive monitoring techniques for quality assurance of cementitious materials; (viii) waste acceptance criteria
for waste packages, waste forms and backfills; transport, long term storage and disposal requirements; and finally (ix) modelling
or simulation of long term behaviours of cementations materials used for packaging, waste immobilization and backfilling,…
2) ELUTION BEHAVIOR OF HEAVY METALS FROM CEMENT SOLIDIFIED PRODUCTS
OF INCINERATED ASH WASTE (wP-59102)
Yoshihiro Meguro, Yoshimi Kawato, Takuya Nakayama,Osamu Tomioka,
Motoyuki Mitsuda, Japan Atomic Energy Agency (Japan)
Combustible radioactive wastes generated from the operation of nuclear facilities are incinerated for volume reduction in
Japan. In Japan Atomic Energy Agency (JAEA) the incinerated ash is planned to be solidified using cement and to be buried in the
ground. Incinerated ashes with various compositions and properties are generated because there are facilities of several kinds of
types such as reactors, nuclear fuel cycle facilities, and hot laboratories in JAEA. And also a small amount of heavy metal, which
is hazardous chemical substance for environment, is also included in the incinerated ash.
The authors push forward a study to determine conditions to produce solidified products of the incinerated ash with cement.
Here relationships between solidification conditions and solidification characteristics have been investigated. The solidification
conditions are the ash composition, cement materials, ash filling rate and water/cement ratio, and the solidification characteristics
are including curing rate and expansion behavior. And also characteristics of the solidified product have been studied, these are
compressive strength, elution behavior of radionuclides and the heavy metals from the solidified products, gas generation by radiolysis,
and so on.
In the present paper, our recent results about the elution behavior of the hazardous heavy metals from synthetic solidified…
3)IMMOBILISATION OF RADWASTE IN SYNTHETIC ROCK: AN ALTERNATIVE TO CEMENTATION (w/P-59008)
Bernard Rottner, Onet Technologies (France)
SOGETER is a waste conditioning process for Low Level radwaste (LLW) or Intermediate Level radwaste (ILW) like sludge,
soil, ashes, evaporator concentrate, concrete rubble, asbestos, sand, & Usually such radioactive waste is solidified into a cement
matrix, resulting in a factor 2 to 5 volume increase: 1 m3 of initial raw waste generates 2 to 5 m3 of solidified waste.
Sogeter consists in melting the waste at high temperature, up to 2000 K, and producing a synthetic rock. The main component
of the matrix is the waste itself; therefore 1 m3 of initial raw waste generates only 0.2 to 0.5 m3 of solidified waste.
Compared to cementation, synthetic rock decreases the volume to be disposed of by a factor of 4 to 25.
By mixing different types of waste, or using additives, the composition of the waste is adjusted, so that a fluid melt is obtained
at temperatures less than 2000 K, and so that the final 200 L ingot may be cooled down within 2 days, without shattering or disaggregating.
We tested a wide range of compositions, demonstrating that almost every type of waste may be conditioned with Sogeter.
We designed the industrial facility, based on a very robust and…
SESSION 24 — L/ILW WASTE CHARACTERIZATION, ASSAY, AND TRACKING SYSTEMS - PART 1 OF 2 (1.7)
1) A PROPOSED FIGURE OF MERIT FOR EVALUATING THE PERFORMANCE
OF RADIATION IDENTIFICATION AND DETECTION SYSTEMS (wP-59159)
Ronald Keyser, Timothy Twomey, ORTEC - AMETEK; Michael D. Belbot, Thermo Fisher Scientific;
Neil Andrew Webster, Thermo Fisher Scientific, Radiation Measurement & Security Instruments (USA)
The instruments used to monitor the radioactive content of waste materials, either in container monitors, hand held radiation
detectors, or mobile analysis systems, are constructed of widely different ways with widely varying detector materials and analysis
software. However, within the various groupings (e.g., automatic waste monitors), all instruments are expected to solve the same
problem, that is, to detect and identify any radioactive material present according to the prescribed investigation methods. The best
way to compare the performance of different instruments is with a numerical score or Figure of Merit (FOM). The FOM must quantity
the performance of the instrument with respect to false positives (FP) and false negatives (FN). The minimization of FN for
certain radionuclides (e.g., uranium and plutonium or SNM) is more important than the minimization of FN for non-threat nuclides
(e.g., low NORM). Likewise, the minimization of FP for SNM is also more important than falsely reporting the common NORM
nuclides. The performance depends on the details of the testing, so the analysis conditions must also be included in the statement
of the FOM. A FOM has been developed based on the number of true positives (TP), the number of false important positives (FIP),
the number…
2) CHARACTERIZATION OF LEGACY LOW LEVEL WASTE AT THE SVAFO
FACILITY USING GAMMA NON-DESTRUCTIVE ASSAY AND X-RAY
NON-DESTRUCTIVE EXAMINATION TECHNIQUES (wP-59289)
Stephen Halliwell, VJ Technologies Inc;
Gary Mottershead, VJ Technologies Inc; Fredrik Ekenborg (USA/France/Sweden)
Over 7000 drums containing legacy, low level radioactive waste are stored at four SVAFO facilities on the Studsvik site which
is located near Nyköping, Sweden. The vast majority of the waste drums (>6000) were produced between 1969 and 1979. The
remainder were produced from 1980 onwards.
Characterization of the waste was achieved using a combination of non-destructive techniques via mobile equipment located
in the AU building at the Studsvik site. Each drum was weighed and a dose rate measurement was recorded. Gamma spectroscopy
was used to measure and estimate radionuclide content. Real time xray examination was performed to identify such prohibited
items as free liquids.
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Session 24 Abstracts
3) CALIBRATION AND VALIDATION OF A WIDE RANGE SEGMENTED GAMMA RAY SCANNING
INSTRUMENTS FOR THE MEASUREMENT OF LOW AND INTERMEDIATE LEVEL WASTE (wP-59304)
John Mason, A. N. Technology Ltd.;
Kapila Fernando, ANSTO, Australia Nuclear Science and Technology Organization (UK/Australia)
This paper describes the design and operation of a Wide Range Segmented Gamma ray Scanning (WR-SGS) assay instrument
for the measurement of both Low and Intermediate Level Waste (LLW and ILW) in 200 liter drums. The instrument employs a single
shielded and collimated high purity germanium (HPGe) detector to quantify the radionuclide content of the waste. A novel feature
of the instrument is the use of an automated variable aperture collimator, which allows the vertical segment height to be adjusted.
Conventional SGS measurements may be performed where the drum is rotated and measured in vertical segments. Alternatively,
faster measurement can be made using continuous helical scanning of the drum as it rotates. Intermediate level waste drums,
with significant surface dose rates, can be measured through the use of the variable aperture collimator. A gamma ray emitting transmission
source is used to correct for waste density. In place of a conventional shutter, the shielded transmission source is moved to
a shielded storage position to eliminate background radiation arising from the transmission source. Using this approach, higher
activity transmission sources may be used in order to achieve adequate density corrections for higher density drums.
These new features makes the WR-SGS suitable for…
4) PERFORMANCE OF A DRUMSCAN® HRGS SOLO SCANNER FOR THE ASSAY
OF LEGACY WASTE AT THE BELGOPROCESS SITE (wP-59122)
Daniel Parvin, Babcock International Group; Thomas Huys, Belgoprocess, Dessel, (UK/Belgium)
On the sites of Belgoprocess several thousands of drums containing conditioned legacy waste are stored. A significant number
of these waste packages are 220 litre drums containing radioactive waste embedded into inactive bitumen. Most of the radioactive
waste in these drums was generated during the development and production of MOX-fuels and the operation of the Eurochemic
reprocessing plant. The current state of a number of these packages is no longer acceptable for long term interim storage. In order
to make the waste packages acceptable for interim storage a repackaging process was developed. The process involves the re-packaging
of the waste items into 400 or 700 litre waste drums and a non-destructive gamma-ray assay (NDA) measurement performed
on the new package. The aim of the NDA measurement is to detect significant quantities of fissile material in order to demonstrate
compliance with the operational limits of the storage building. Since the waste items are destined for geological disposal, there is
no specific need for a detection limit in the order of milligrams of plutonium as required for surface disposal.
To meet this NDA requirement Babcock International Group supplied, calibrated and commissioned an open geometry version
from its HRGS product range. The DrumScan®…
SESSION 25 — D&D OF NON-REACTOR NUCLEAR FACILITIES (3.10)
1) DECOMMISSIONING THE BELGONUCLEAIRE DESSEL MOX PLANT: PRESENTATION
OF THE PROJECT AND SITUATION ON 30/06/2011 (wP-59027)
Jean-Marie Cuchet, Carlo Verheyen, Henri Libon, Belgonucleaire; Jos Custers, Tecnubel; Robert Walthery,
Belgoprocess; Jozef Bily, Studsvik (Germany)
BELGONUCLEAIRE has been operating the Dessel MOX plant at industrial scale between 1986 and 2006. In this period, 40
metric tons of plutonium (HM) have been processed into 90 reloads of MOX fuel for commercial light water reactors. The decision
to stop the production in 2006 and to decommission the MOX plant was the result of the shrinkage of the MOX fuel market
owing to political and customers factors.
As a significant part of the decommissioning project of the Dessel MOX plant, about 170 medium-sized glove boxes and about
1.300 metric tons of structure and equipment outside the glove boxes are planned for dismantling.
The license for the dismantling of the MOX plant was granted by Royal Decree in 2008 and the dismantling started in March
2009; the dismantling works are executed by an integrated organization under leadership and responsibility of BELGONUCLE-
AIRE with 3 main contractors, namely Tecnubel N.V., the THV Belgoprocess / SCK•CEN and Studsvik GmbH
In this paper, after having described the main characteristics of the project, the authors introduce the different organisational
and technical options considered for the decommissioning of the glove boxes, and the main decision criteria (qualification of personnel
and of processes, confinement, cutting techniques…
2) URANIUM WORKSHOPS DISMANTLING AND CRITICALITY CONTROL (wP-59060)
Pierre Lisbonne, Julie Rosello, CEA (France)
Within the CEA at Cadarache Research Center located in southern France, the ATUE, standing for Ateliers de Traitement de
lUranium Enrichi (Enriched Uranium Treatment Workshops), is a nuclear facility started in 1965, and shut down in 1995.
Various chemical processes were in operation in the ATUE in order to product enriched uranium oxide intended for fast breeders
and naval propulsion reactors.
According to the mass of fissile material, the most contaminated process equipment has already been dismantled under criticality
risk management procedures. Cleanup of the building and dismantling of the remaining equipment, such as ventilation and
electricity network, are now in progress without any constraint regarding criticality, thanks to in site measurement and calculations.
Criticality management and how we finally proved the risk was over, as well as the strategy under French rules for final decommissioning
of the facility leading to brown field will be presented.
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Abstracts Session 25
3) THE COMPLEX CHALLENGE OF REFURBISHING THE POND GANTRY STEELWORK
WHICH SUPPORTS THE POND SKIP HANDLER ABOVE THE FIRST GENERATION
MAGNOX STORAGE POND AT SELLAFIELD (wP-59133)
Ian Richardson, Sellafield (UK)
The First Generation Magnox Fuel Storage Pond (FGMSP) provided fuel storage and decanning capability from the early
1960s until 1986.
A significant programme of work has been underway since the completion of operational activities to support the programmes
strategic intent of retrieving and storing all legacy wastes, and remediating the structure of the plant to support decommissioning
activities.
A key enabler to the retrievals programme is the Pond Skip Handler Machine (SHM), removed from service in 2002 following
the discovery of significant signs of corrosion, an inevitable consequence of being located in a coastal, salt laden environment.
The SHM provides sole capability to access and retrieve the inventory of the fuel skips in the pond. It is also fundamental to
future operations and the deployment of desludging equipment to recover bulk sludges from the pond floor.
This paper will examine the challenges faced by the team as they successfully defined, planned and executed remedial work
to a specific aspect of the civil structure, the SHM gantry rail system, using a purpose built refurbishment platform; the Gantry
Refurbishment System.
The paper will examine how an innovative approach was adopted to resolve the related issues of:
• Refurbishing an aged structure to….
4) SYSTEMATIC CHEMICAL DECONTAMINATION USING IF7 GAS (wP-59036)
Haruhi Hata, Kaoru Yokoyama, Noritake Sugitsue, Japan Atomic Energy Agency (Japan)
Since 1979, Uranium enrichment technology has been researched through the gas centrifuge method, at Ningyo-toge Environmental
Engineering Center of Japan Atomic Energy Agency(JAEA). In addition, the Demonstration Plant, that is final stage test
facilities, was operating continuously from 1988 to 2001.
As a result, a lot of residues accumulated in the plant. Most of this accumulation was found be uranium intermediate fluoride.
The basic decommission policy of JAEA is that equipments of gas centrifuge will be decontaminated by sulfuric acid immersion
method for clearance and reuse.
In our plan, approximately 90% of metals will be cleared and reused, and then the remaining 10% will be disposed of radioactive
waste.
We propose a combination of sulfuric acid immersion method and the systematic chemical decontamination as an efficient
method for decontamination of uranium enrichment facilities. This paper focuses on the method and performance of systematic
chemical decontamination using IF7gas. The following (Figure 1)shows our decommission policy and position of systematic chemical
decontamination by IF7gas for uranium enrichment plant...
5) DECOMMISSIONING & DEMOLITION OF FACILITIES USED FOR THE STORAGE
& STABILISATION OF WATER REACTOR SLUDGE (wP-59097)
Nicholas J. Brown, Rowland Cornell, Nuvia Limited; Andy Staples, RSRL (UK)
Nuvia Limited was contracted to design, build and operate a waste treatment plant to stabilise a quantity of about 300m3 of
active sludge stored in the External Active Storage Tanks (EAST) at the former United Kingdom Atomic Energy Authority
(UKAEA) research site at Winfrith, UK. At the end of this process both the old and new plants are to be decommissioned and
demolished with the minimisation of waste material volumes. The sludge was produced in the Steam Generating Heavy Water
Reactor (SGHWR) during 30 years of operation, which is now in the early stages of decommissioning. As part of the reorganisation
of UKAEA responsibility for the site now lies with RSRL (Research Sites Restoration Limited) with funding provided by the
Nuclear Decommissioning Authority (NDA).
The process of stabilisation of the SGHWR sludge from the EAST tanks within 500 litre stainless steel drums in the newly
constructed Winfrith EAST Treatment Plant (WETP) was completed in March 2010. Now that these operations have been completed,
the plant has entered a full decommissioning phase since no further work on any other waste materials have been identified by
the client.
This paper describes the development of a decommissioning plan for the mixture of old…
6) DECOMMISSIONING OF THE RADIO CHEMICAL HOT LABORATORY OF THE
EUROPEAN COMMISSION JOINT RESEARCH CENTRE OF ISPRA (wP-59207)
Daniele Ugolini, Francesco Rossi, Francesco Basile, European Commission Joint Research Centre (Italy)
The construction of the Radio Chemical Hot Laboratory (RCHL) of the Joint Research Centre (JRC) of Ispra began in the early
1960s while the laboratory activities started in 1964. In 1976 an annex to the main building was built. At this time the RCHL main
research activities were in environment and biochemistry by means of radioactive tracers; neutron activation analyses; extraction
of actinides from radioactive liquid waste coming from the nuclear fuel reprocessing plants; and analyses of U, Pu, and Th in samples
from the nuclear fuel cycle in order to determine the isotopic ratio and the burn-up. In 1978, a new area of laboratories named
Stabularium was built to study the metabolism of heavy metal on laboratory animals. Complementary to the laboratory three pneumatic
transfer systems for irradiated sources connected the RCHL to two research reactors.
The decommissioning activities of the 2650 m2 facility started in January 2008 and they were completed at the end of 2010
with the release for unrestricted use of all the buildings of the facility. They consisted in five main tasks: pre-decommissioning,
licensing, dismantling, waste management, and final survey. The main pre-decommissioning activities were the physical and radiological
characterization of the facility. The principal…
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Session 26 Abstracts
7) A SUCCESSFUL TRANSITION FROM OPERATING TO DISMANTLING
A UO2-PUO2 FUEL FABRICATION FACILITY (w/oP-59326)
Thierry Flament, AREVA NC (France)
After fabricating plutonium fuels for 40 years (Fast bredder reactor, Mox), commercial operations at the AREVA Cadarache
plant ended in 2003 and post operation clean out of its production building and laboratory started. AREVAs objective is to achieve
the clean-up of the process facilities and to transfer them to their owner, the French Atomic Energy Commission. The completion
of this operation demonstrates the possibility to dismantle plutonium fuel fabrication facility and the possibility to reuse the facilities.
The facilities to be dismantled by AREVA at Cadarache include:
About 420 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),
• About 40 storage tanks
• 3 major steps in this large D&D programme
• Recovery of fissile materials left in the facility led by a project team:
• 25 metric tons of mixed oxide materials in the various glove boxes / storage were recovered in less than 5 years...
SESSION 26 — D&D TECHNOLOGIES - PART 1 OF 2 (3.4)
1) DISMANTLING/REMEDIATION OF A HIGHLY CONTAMINATED SUMP
IN RUNNING PLANT CONDITIONS (w/oP-59053)
Jos Boussu, Koen Lenie, Tecnubel (Belgium)
A sump in the RPE circuit in the EDF - Nuclear Power Plant of Cruas-Meysse, showed a extremely high radiation dose rate
since 2007.
Different attempts to decontaminate the sump did not have the desired effect.
The sump is a so-called gatte where two flows of different fluida circulates. A chemical flow transverses the sump within stainless
steel piping, the second flow which is (contaminated) residual water, flows through this sump in contact with the sumps walls.
The dose rate was estimated at 20 Sv/h, and it was presumed being a single hotspot in the dead zone of the sump, where no
chemicals from the chemical decontamination attempts, and no high pressure water contact had been possible, or had any effect.
To protect the maintenance and exploitation people from the radiation, the sump had been protected with a physical protection
system, named a sarcophage. The client asked to leave this protection system, which was modular, on place during the dismantling
works to assure its radiation protection function.
The paper describes the remote controlled dismantling of the sump within the particular running conditions of the power plant,
the developments made to the equipment, and the conditions in which the works had to be carried out.
Some lessons learnt and particular points of attention are revealed to complete this paper.
2) NEW DEGREASING FORMULATIONS FOR THE DECONTAMINATION OF SOLID SUBSTRATES,
CONSISTENT WITH VITRIFICATION PROCESS OF THE FINAL WASTES (w/oP-59166)
Jeremy Causse, Cyril Roussignol, French Atomic Enrgy Commission; Jean-François
Valery, Jean Charles Hamel, Areva NC (France)
Decontamination shops use various techniques to decontaminate solid substrates. The aim of these shops is either to recover
the substrate for a future second life, or to sufficiently lower the radioactivity level in order to reduce the final waste volume. One
of these techniques remains in aqueous bathes possibly under ultrasonic agitation. This technique is very fit to small metallic pieces.
Most of those pieces are covered with various greases or organic oils very resistant to classical aqueous washes. Thus, this oily
layer contains some unfixed radionuclides that must be removed to reach the decontamination factor targeted. This urged decontamination
shops operating staff to consider additive molecules necessary to render aqueous washes consistent with such a contamination.
These molecules, namely surfactants, act on the liquid surface to increase affinity between aqueous and oily phases.
The surfactant formulations used in French decontamination shops are industrial formulations. Those formulations are generally
designed by international manufacturers to be consistent with several applications. Thus, there isnt any specific formulation fitted
to nuclear applications. But, this way of working is no longer possible now. This is due to the changes of final wastes conditioning
matrix. Indeed, bitumen matrix is devoted to disappear in the next…
3) THE ORION SCANSORT SOIL SORTING SYSTEM (w/oP-59385)
Jeffrey Lively, MACTEC (USA)
Radiologically contaminated sites undergoing remediation or decommissioning typically have large volumes of soil which are
heterogeneously contaminated by radioactivity from historic operations. There is a severe shortage of available disposal space for
this type of material worldwide. It is, therefore, important that volumes being disposed are minimized as far as possible to ensure
efficient use of scarcely available radioactive waste disposal facilities. There are also significant cost savings to be realized 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.
The 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 programs 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 MACTECs state-of-the-science bulk soil survey and sorting system
developed and successfully used in the USA…
86

Abstracts Session 26
4) LIQUIDS, GELS, FOAMS AND SUPERCRITICAL FLUIDS: FOUR STATES OF MATTER
FOR RADIOACTIVE DECONTAMINATION OF SOLIDS (w/oP-59158)
Sylvain Faure, Jérémy Causse, Bruno Fournel, CEA (France)
To face the future challenges in the nuclear industry as dismantling and decommissioning, the Advanced Decontamination
Processes Laboratory (Laboratoire des Procédés Avancés de Décontamination - LPAD) from the French Atomic Energy Commission
(CEA) is developing new radioactive decontamination of solids processes to protect workers and to reduce strongly the quantity
of secondary wastes produced. We have focused in the last past years on the use of four states of matter to develop new patented
nuclear decontamination processes: micellar aqueous solutions, gels, foams and supercritical fluids.
The conference gives an overview of these four ways to decontaminate a solid surface. The major applications and results
obtained on real decontamination operations will be presented for each process. First, micellar solutions based on copolymers
blocks surfactants are presented for radioactive degreasing. The advantage to formulate self-drying and cracking gels films sprayed
on metallic surfaces is then detailed. For decontamination foams, an approach using new additives polymers or particles- is
defended to obtain high life time foams that are able to treat huge and complex shape materials such as fission products tanks or
steam generator. At the end, original works to treat textiles or gloves boxes using surfactants in CO2 supercritical fluid are given.
Finally, the major challenges to develop more secure processes and to reach a better decontamination efficiency are given.
5) DECOMMISSIONING OF THE A-1 NPP HEAVY WATER EVAPORATOR FACILITY (wP-59225)
Jan Medved, VUJE Inc.; Ladislav Vargovcik, ZTS VVU Kosice a.s. (Slovakia)
The paper deals with experience and techniques in the application of remotely controlled robotic devices for the dismantling
of the A-1 NPP technological equipment during undergoing decommissioning process of the A-1 NPP, which is characterized by
high level of radioactivity and contamination. For liquidation of the heavy water evaporator has been applied a mobile robotic system
MT 80, which had been developed, designed and constructed as a general-purpose decommissioning equipment. The heavy
water evaporator as a part of the NPP heavy water system is located inside the main production unit building in Room No. 220
where the inner surface contamination is from 101 Bq/cm2 to the level of 103 Bq/cm2 , dose rate up to 1.5 mGy/h and the feeding
pipeline contained LRAW with high tritium content.
The first step was the development of a work procedure with special focus on the elimination of activity and aerosols leaking
into the environment. Special tooling was developed for application with the robot, such as hydraulic shears, circular saw, reciprocating
saw, circular pipe cutter and a system for quick tool-change without direct intervention of the operators. Then, civil engineering
modifications were made to the workplace and new technology was installed, including an efficient exhaust…
6) REMOTE DECOMMISSIONING OF BLIND CELLS - APM 214 FACILITY CEA MARCOULE (w/oP-59206)
Olivier Calixte, ONET Technologies - ONECTRA (France)
The APM 214 facility (Marcoule Pilot Workshop) owns blind cells which were used to realize some chemical process operations.
These ones are at their end of life and D&D operations are planned.
Due to the high level of radiations these operations must be partially realized with remote machines. The CEA has entrusted
ONECTRA, a subsidiary of ONET TECHNOLOGIES to define the best way to dismantle these blind cells by remote operations.
The first step started with an inventory of main physical characteristics, constraints, nature of remote operations to do and possible
tools.
7) TRANSPORT OF NUCLEAR WASTE FLOWS - A MODELING AND SIMULATION APPROACH (wP-59136)
Jonathan Adams, Michael Fairweather, James Young, Simon Biggs, Jun Yao, University of Leeds, Leeds (UK)
The task of implementing safer and more efficient processing and transport techniques in the handling of nuclear wastes made
up of liquid-solid mixtures provides a challenging and interesting area of research. The radioactive nature of nuclear waste means
that it is difficult to perform experimental studies of its transport. In contrast, the use of modelling and simulation techniques can
help to elucidate the physics that underpin such flows and provide valuable insights into common problems associated with them,
as well as assisting in the focussing of any experimental studies. With nuclear waste in the form of solid-liquid sludges it is important
to understand the nature of the flow, with particular interest in the settling characteristics of the particulate waste material.
Knowledge of the propensity of pipe flows to form solid beds is important in avoiding unwanted blockages in pipelines and pumping
systems. In cases where the formation of a solid bed is unavoidable, it is similarly important to know how the modified crosssectional
area of the pipe, due to the presence of a bed, will affect particle behaviour through the creation of secondary flows. A
greater understanding of particle deposition in pipes of circular cross-section is also of significant and…
8) FUEL RACKS DISMANTLING WORKSHOP AT CENTRACO FACILITY (wP-59365)
Jean-François Rives, Christophe Maufrais, SOCODEI (France)
Initial context: EDF aims to replace all the ancient storage racks to gain place in the fuel ponds. This project represents about
450 units up to 4m x 4,4m x 2,9m, weight 6,4te to dismantle, during 5 years The average density of the racks is very low (approx
~ 0.15). Due to this low density, final repository route is not adapted. By its knowledge and capabilities, CENTRACO route was
chosen to reduce volume, restore density, decontaminate & secure the elimination of the racks. With those data, CENTRACO has
defined the ATG workshop to dismantle racks but also wide components as steam generators. It was designed with as much automated
devices and skills as possible, in order to avoid dose rate and contamination and to save time. It is currently under construction
and will be put in operation in the early 2012.
87

Session 27 Abstracts
SESSION 27 — ER SITE CHARACTERIZATION AND MONITORING - PART 1 OF 2 (4.5)
1) SOILS RADIOLOGICAL CHARACTERIZATION UNDER A NUCLEAR FACILITY (wP-59046)
Emilie Aubonnet, Geovariances / CEA FAR, Fontenay aux Roses, France,
Didier Dubot, CEA/FAR/USLT/SPRE/SAS, Fontenay aux Roses (France)
Nowadays, nuclear industry is facing a crucial need in establishing radiological characterization for the appraisal and the monitoring
of any remediation work. Regarding its experience in this domain, the French Atomic Energy Commission (CEA) of Fontenay-aux-Roses,
established an important feedback and developed a sound methodology for radiological characterization.
This approach is based on several steps: • historical investigations • assumption and confirmation of the contamination • surface
characterization • in depth characterization • rehabilitation objectives • remediation process
In this methodology the amount of measures, samples and analysis is optimized for data treatment by geostatistics. This innovative
approach is now used to characterize soils under facilities. In Fontenay-aux-Roses CEA Centre, there is an action plan aiming
to assess the activity level under accessible facilities. The paper presents the radiological characterization of soils under RM1
basement. This facility has been built after the first generation of nuclear facilities in place of a plutonium facility which has been
dismantled in 1960. The presentation details the different steps of radiological characterization from historical investigations to
optimization of excavation depths, impact studies and contaminated volumes.
2) RADIOLOGICAL EVALUATION OF CONTAMINATED SITES AND SOILS VEGAS:
AN EXPERTISE AND INVESTIGATING VEHICLE (wP-59057)
Julien Attiogbe, GEOVARIANCES; Marie Lavielle, Patrick De Moura, CEA (France)
The "Commissariat à l’Energie Atomique" (CEA, French Atomic Energy Commission) has set up over the last 10 years
an innovative methodology aiming at characterizing radiological contaminations. The application of the latter relies on various tools
such as recently developed software platform called Kartotrak which is used in the expertise vehicles with impressive detection performances
(VEgAS). A Geographic Information System tailored to radiological needs constitutes the heart of the platform; it is surrounded
by several modules dedicated to sampling optimization, data analysis and geostatistical modeling, real-time monitoring
(Kartotrak-RT) and validation of proper clean-up operations. This paper presents the purpose and the performances of the VEgAS
which provides exhaustive instruments for the radiological surface characterization of sites.
3) DETERMINATION OF THE RADIONUCLIDE CONTAMINATION
ON THE ABSHERON PENINSULA IN AZERBAIJAN (wP-59177)
Tjalle Vandergraaf, Providence University College; Gudrat G Mamedov, Mahammadali A. Ramazanov,
Baku State University; Jalal A. Naghiyev, Institute of Radiation Problems; Afat A. Mehdiyeva, National Aerospace
Agency of Azerbaijan; Nazim A. Huseynov, Institute of Radiation Problems (Canada/Azerbaijan)
Much of Azerbaijans Absheron Peninsula is contaminated by natural U-series and Th-series radionuclides, released in the production
of oil and gas and, to a lesser extent, by anthropogenic radionuclides, including Sr-90 and Cs-137, from local industrial
activities and trans-border transport. The region contains a large number of pipelines and artificial lagoons that have been used to
retain excess groundwater and oil residues. In spite of the long history of the oil and gas industry, radioecological investigations
have not been carried out until recently.
The purpose of the current project is to determine the extent of radionuclide contamination in the Absheron Peninsula using a
combination of radiation field measurements and laboratory analysis of selected samples, focusing on ten routes in the vicinity of
Baku. The routes were selected as most likely to have become contaminated over time. Soil samples, taken from surface and to a
depth of 1 m, aqueous samples from surface waters and marshes, and aqueous and sediment lagoons that showed elevated dosimetry
readings, were analyzed by gamma spectrometry. Control samples were taken form non-contaminated areas. Samples of air and
surface waters were analyzed for Rn-220 and Rn-222. The data will then be used to assess the potential impact
4) HIGH-DENSITY GAMMA RADIATION SPECTROMETRY SURVEYS OF CONTAMINATED LAND (wP-59076)
Mike Davies, Robert Clark, Ian Adsley, Nuvia Limited (UK)
The design of gamma radiation surveys of contaminated land has always had to compromise between the density of sampling
and the accuracy of measurement. Large-area contamination is readily detected by a variety of measurement techniques, while the
detection of small areas or particles requires a high density of measurement, generally one measurement per square metre.
High Resolution Gamma-radiation Spectrometry (HRGS) can provide accurate qualitative (radionuclide identification) and
quantitative (Bq.g-1 of the radionuclide for a stated scenario) assessment of the state of the land, but are not cost effective at high
density. In contrast, simple walk-over or scan surveys using standard Health Physics instruments can provide a high density of
measurement, but cannot provide the qualitative and quantitative accuracy of HRGS. In 1996, Nuvia Limited adopted methods to
address some of these issues, by allowing scan surveys to include a degree of qualitative analysis of the gamma radiation detected
using Low Resolution Gamma-radiation Spectrometry systems with Sodium Iodide detectors, while maintaining a high density of
measurement.
While low-resolution systems (including medium-resolution Lanthanum Bromide) have become the de-facto standard for large
area land surveys, the use of the technology has changed little. High density scan surveys can be conducted using, for example,…
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Abstracts Session 27
5) REMEDIATION AND ASSESSMENT OF THE NATIONAL RADIOACTIVE WASTE
STORAGE AND DISPOSAL SITE IN TAJIKISTAN (wP-59110)
Nazirzhon Buriev, Dzhamshed Abdushukurov, Physical-Technical Institute of the Academy of Sciences
of the Republic of Tajikistan; Tjalle Vandergraaf, Providence University College (Tajikistan/Canada)
The National Radioactive Waste Storage and Disposal Site was established in 1959 in the Faizabad region approximately 50
km east of the capital, Dushanbe. The site is located on the southern flank of the Fan Mountains facing the Gissar Valley in a sparsely
populated agricultural area, with the nearest villages located a few km from the site. The site was initially designed to accept a
wide range of contaminated materials, including obsolete smoke detectors, sealed radioactive sources, waste from medical institutions,
and radioactive liquids.
6) INTEGRATING HISTORY AND MEASUREMENT INTO A CASE FOR SITE RELEASE (wP-59131)
Angela Bartlett, Research Sites Restoration Limited; Mike Davies, Pete Burgess, Nuvia Ltd;
Gavin Coppins, Babcock International Group (UK)
The United Kingdom nuclear research programme started in the 1940s. Research Sites Restoration Limited (RSRL) is responsible
for two sites which were at the forefront of this research. These are the 100 hectare Harwell site in Oxfordshire and the 84
hectare Winfrith site on the south coast of England. The work performed on these sites covered a huge range of nuclides, combinations
of nuclides, chemical and physical processes, far more complicated than a power station, for example. The sites have a complex
history with records of hundreds of buildings, many kilometres of drainage systems, groundwater contamination issues and
land areas which require remediation. Formal work towards site release began in the 1990s, but demolition and clearance for reuse
started many years earlier.
An efficient restoration programme requires appropriate quality data. It is vital to decide what you need to know and how well
you need to know it. As part of this, a challenging number of factors need to be considered in its design.
This paper discusses these factors using the examples of the approach used at the Harwell and Winfrith sites including:
• historical knowledge and associated uncertainties
• relevant clearance criteria
• availability and limitations of surveying equipment...
7) CHARACTERIZATION OF A DEEP RADIOLOGICAL CONTAMINATION:
INTEGRATION OF GEOSTATISTICAL PROCESSING AND HISTORICAL DATA (wP-59062)
Yvon Desnoyers, GEOVARIANCES; Patrick De Moura, CEA (France)
Emerging in the early 80s, decommissioning is more than ever a major issue since hundreds of sites and facilities worldwide
will end their operations over the next decades. Decontamination and remediation projects are all the more sensitive since they
could last several years and turn out to be highly costly if not well-prepared. The key lies in an adequate contamination knowledge
which helps to manage the remediation works and optimize the radiological waste production.
The methodologies commonly applied base their recommended decision-process on more or less complex statistical analyses
to validate the remediation target after the waste removal work (guidance for demonstrating compliance with a dose- or risk-based
regulation). These techniques ignore the spatial behavior of the contamination and the importance of sample localization upstream.
The lack of representation and data processing tools leads to inefficient radiological characterizations, which always maximize the
amount of contaminated soils or concrete volumes.
To solve these issues, the French Atomic Energy Authority (CEA) has developed a methodology over the last 10 years with
Geovariances partnership to fulfill the radwaste categorization. This methodology consists of an ordered sequence of evaluation
actions starting with historical and functional analyses, in-situ characterization if relevant using non-intrusive measurement techniques,
...
8) INDUSTRIAL EXPERIENCE FEEDBACK OF A GEOSTATISTICAL ESTIMATION
OF CONTAMINATED SOIL VOLUMES (wP-59181)
Claire Faucheux, Nicolas Jeannée, GEOVARIANCES(France)
Data collected during the sampling of polluted sites are mainly used to characterize the concentration level and, through an
exploratory and variographic analysis, to characterize the spatial variability; at fixed support, to estimate the concentrations in order
to trace pollution map. In the case of kriging, this map is completed by the map of the standard deviation of the estimation error,
making it possible to delimit the zones in which the estimation is considered to lack in precision. If a proportional effect is present
(the local spatial variability depends on the local concentrations mean), the map of error standard deviation has to be corrected to
take into account the increase of spatial variability with the local concentration mean.
A confidence interval can be derived conventionaly from the kriging estimation and the associated error standard deviation.
For a fixed limit threshold, the polluted site can then be divided in three areas:
• the polluted zone, at a fixed statistical risk;
• the not polluted zone, at a fixed statistical risk;
• the zone of uncertainty , in which the estimated concentrations are close to the threshold. Because of the estimation error,
it is not possible to specify if the exact concentrations exceed or not the threshold.
In the case of a soil pollution by hydrocarbons, usual and geostatistical forecasts are compared. The effective consequences of
these various forecasts on the quality of the site remediation are quantified and discussed.
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Session 28 Abstracts
SESSION 28 — PUBLIC PERCEPTION ISSUES AND STAKEHOLDER ENGAGEMENT STRATEGIES
IN RADIOACTIVE ENVIRONMENTAL MANAGEMENT (5.5)
1) PERSPECTIVES ON REVERSIBILITY AND RETRIEVABILITY OF A
GEOLOGICAL REPOSITORY IN FRANCE (wP - 59263)
Jean-Noel Dumont, Jean-Michel Hoorelbeke, Andra (France)
In France it is required by law that the future geological repository for HLW and ILLW be reversible. Reversibility reflects
social and political demand. The law, however, does not provide conditions for implementing reversibility. Instead, it calls upon
scientists to issue specific proposals before a new law is promulgated as a preliminary to obtaining authorization to build a waste
repository. A dialogue between various players, scientists and stakeholders is required to prepare these proposals. It gives designers
of the repository the opportunity to assess social expectations and integrate them. It is also an opportunity to examine together
possible technologies, as well as scientific and technical limits. Andra is involved in various forms of dialogue with social players.
Several expectations related to reversibility have been detected by Andra through this dialogue. Reversibility means in particular
retrievability of waste package(s) once disposed, which could be envisaged if future technical progress makes it re-useable, to
switch to another mode of waste management, or if the repository does not evolve as planned. More generally, the demand for
reversibility reflects the desire to control evolution of the process and make sure that the repository will not be abandoned after closure.
These expectations call for answers…
2) A DIALOGUE-CENTRIC APPROACH TO ENVIRONMENTAL REMEDIATION DECISION-MAKING (wP -59115)
Laurel Boucher, The Laurel Co.; James Clark, CRX Group, Inc. (USA)
This paper outlines a multi-step approach to streamline and enhance the decision-making process that guides environmental
remediation. The inability of the responsible party and the various stakeholders to reach agreement on the remediation plan can
delay the remediation, result in financial penalties, and lead to the development of an adversarial stance that inhibits the ability of
the parties to work together in a creative and constructive manner. The approach presented by the authors is designed to expand
dialogue in a way that moves it beyond technical or fiscal matters by addressing what the authors describe as the hidden barriers
to productive dialogue. These hidden barriers include: self-interests, the perception as to how people are being treated, a lack of
clarity or poor management of responsibilities and accountabilities, unclear or convoluted communication protocols, and an underlying
tone of conflict and cynicism. A key element of the multi-step approach outlined in this paper is the process of uncovering
these hidden barriers and addressing them in a way that turns discourse into collaboration.
The paper describes a model the authors have used to streamline and enhance the process of creating sustainable agreements
both for the U.S. Department of Energys Office of Environmental Management…
3) OUTREACH AND EDUCATION - ENSURING A CLEAN ENERGY FUTURE FOR ALL (wP - 59339)
Susan Hess, Areva Inc USA)
As the nuclear industry continues to grow throughout the world, we find that support from government officials, local business
leaders and the general public is becoming more and more important.
In order to help raise awareness and inform these various publics, AREVA expanded upon a best practice from its worldwide
operations and recently established a Community Advisory Council in the United States. The member organizations represent a
variety of grassroots and minority organizations from across the United States and are active in various ways in local, state and federal
arenas.
4) CHALLENGE IN THE PUBLIC ACCEPTANCE AND COOPERATION IN THE VERGE OF
BUILDING THE FIRST NUCLEAR POWER PLANT IN INDONESIA (wP - 59119)
Putero Susetyo Hario, Santosa Haryono Budi, Gadjah Mada University (Indonesia)
Indonesia plans to build the first nuclear power plant (NPP) to solve the country’s energy problems. One of the challenges that
must be handled before establishing the first NPP is the presence of anti-nuclear groups that have successfully made the government
postpone its plan several times since the first nuclear research reactor was established in Bandung (1972). The basis for the
groups’ dissent is the presence, and handling of radioactive waste. Further, the general public perception – even among educated
Indonesians – is that Indonesia’s experts lack knowledge about nuclear technology, even though nuclear technology has been studied
in Indonesia since 1954.
So, the problem is one of disseminating information about nuclear technology. To address this challenge, the National Atomic
Energy Board (BATAN) of Indonesia has to redesign its public outreach strategy by collaborating with the educational institutions
and communications organizations. Gadjah Mada University is the only university in Indonesia offering a nuclear-engineering curriculum.
Therefore, a teaming arrangement with this institution seems appropriate to help improve the public’s general knowledge
about nuclear technology. There are several strategies that could be designed within the frame work of collaboration. The first strategy
is to introduce nuclear technology into Indonesia’s elementary and secondary schools. These youngsters are still in their formative
years and are absorbing science and technology with great attention.
5) ANDRA LONG TERM MEMORY PROJECT (wP - 59277)
Patrick Charton, Fabrice Boissier, Guillaume Martin, Andra (France)
Long term memory of repositories is required by safety, reversibility and social expectations. Thus Andra has implemented
since 2010 a long-term memory project to reinforce and diversify its current arrangements in this field, as well as to explore opportunities
to extend memory keeping over thousands years.
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Abstracts Session 29
The project includes opportunity studies of dedicated facilities. The écothèque and géothèque projects contribute to memory
respectively through environmental and geological samples preservation. The options of creating (i) an archive centre for Andras
interim and permanent archives, (ii) an artist center to study the contribution of arts to memory preservation, (iii) a museum of
radioactive waste disposal history and technology (radium industry..., sea disposal&, current solutions...) are considered.
Other studies provided by the project examine our heritage. This includes the continuity of languages and symbolic systems,
the continuity of writing and engraving methods, the archaeology of landscapes (memory of the earths evolution, multi-century
memory of industrial and agricultural landscapes&), the archaeology practices (how might a future archaeologist be interested in
our current activity?), the preservation of historical sites and industrial memory, the continuity of institutional organizations, the
memory and history of science evolution as well as broad history.
Significant studies address social issues, such...
6) ENGAGING LOCAL STAKEHOLDERS ON TECHNICAL ISSUES:
TEST CASE AT THE LA HAGUE REPROCESSING PLANT (wP - 59211)
Ludivine Gilli, Institut de radioprotection et de sûreténucléaire (IRSN) (France)
As the French public expert in the nuclear field, the Institute for Nuclear Safety and Radioprotection (IRSN) has for several
years advocated the need to engage citizens on technical issues pertaining to radioactive waste management. This belief in the usefulness
of citizens involvement to enhance nuclear safety has led IRSN to initiate numerous pilot actions in cooperation with local
actors.
In 2009-2010, IRSN tackled a new pilot action regarding the decommissioning of the HAO (High Activity Oxide) workshop,
located on Arevas fuel reprocessing plant site, in La Hague, North-western France. The purpose of that action was to experiment
ways for IRSN and local actors to engage in technical discussions with a concrete objective in mind: contributing to enable the local
stakeholders to take a stand on the operators decommissioning application.
A pilot action was useful here, because the challenges are many when it comes to engaging with citizens on technical matters.
First, there is a significant knowledge and cultural gap between most local stakeholders and the nuclear professionals, which
prevents the formers to get a grip on technical issues. Hence, both parts must make an effort to understand and be understood. The
local actors must moreover build a technical capacity...
7) CREATING AND MANAGING RADIOACTIVE WASTE DISPOSAL FACILITIES
WITH THE INVOLVEMENT OF THE LOCAL POPULATIONS (w/oP - 59286)
Sébastien Farin, Andra (France)
Andra is responsible for proposing and implementing industrial management solutions for all French radioactive waste. Andra
is in particular in charge of operating the two repositories in the Aube region, monitoring the Manche repository one of the world’s
first surface repositories and creating disposal facilities for waste currently without an operational disposal solution.
Andra’s communication approach.
Andra’s communication role is stipulated by law and is an integral part of its activities, in the same way as research, industry
or risk management. Andra’s aim is to make the subject of radioactive waste management one that is of nationwide interest comprehensible
to the largest possible number, so that each citizen and stakeholder can, in full possession of the facts, make his or her
own opinion and finally reach an informed decision.
Andra’s communication policy is based on four main levers:
• Information, through a full range of tools (websites, publications, periodicals) adapted to the level of expertise and understanding
of its various target audiences;
• Explanation, by means of opportunities throughout the year for those interested in the subject (site visits, fairs, meetings
with schools, travelling exhibitions, etc.);
• Local integration, through regular relations with local players and ...
SESSION 29 — PANEL: INTERNATIONAL COOPERATION:
NEA ROAD MAP, HOW TO INCREASE SYNERGY (3.12)
ABSTRACTS NOT REQUIRED
SESSION 30 — SITING, DESIGN, CONSTRUCTION, AND OPERATION
OF L/ILW DISPOSAL FACILITIES - PART 1 OF 2 (1.12)
1) AN INNOVATIVE DESIGN FOR LOW AND INTERMEDIATE RADWASTE NEAR
SURFACE REPOSITORY IN LITHUANIA (w/oP-59382)
Boniface Jean-Michel, AREVA TA (France)
In 2009, in response to an open tender, funded by the European Bank for Reconstruction and Development, a consortium comprising
Lithuanian and French partners led by Areva was selected by Ignalina nuclear power plant (INPP) to design a dedicated
100.000 m3 LILW-SL Near Surface Repository (NSR) planned to be constructed nearby the power plant.
After preliminary siting studies, the site of Stabatiske was selected by the Lithuanian government in 2007. Following this decision,
the projects technical and commercial requirements for the NSR design was prepared by experts from INPP with the support
of the Lithuanian radwaste management agency (RATA).
This NSR is to be developed and engineered for the disposal of INPP radwaste produced by its operation, and arising from its
dismantling. The result of the project is to develop, following IAEA guidelines, an innovative multi-barrier repository design which
is engineered for the Stabatiske site, with the presence of groundwater, for the sites characteristics, comprising clay layers, moraine
deposits and aquifers, and for the volume and type of radwaste, the disposal containers and the engineered barriers. This design is
on schedule for completion in 2013, and will provide the basis for the construction of the repository, the first facilities of…
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Session 30 Abstracts
2) PRODUCT QUALITY CONTROL OF RADIOACTIVE WASTE WITH A SPECIAL REGARD
TO FEDERAL STATES COLLECTING FACILITIES (w/oP-59176)
Markus Havertz, Research Centre Jülich GmbH (Germany)
The KONRAD repository for low- and intermediate level radioactive waste is the first disposal facility approved by the Atomic
Energy Act in Germany.
For final disposal the radioactive waste products or waste packages have to meet the acceptance criteria of the final repository
KONRAD.
On behalf of the Federal Office for Radiation Protection the quality control group (PKS) at Research Centre Jülich accomplishes
the product quality control of non-heat producing waste, which mainly arises from generation of electricity by nuclear power
plants, research and development activities, medicine and industry, as well as decommissioning and dismantling of nuclear facilities.
The product quality controlling process includes varies steps, inter alia checks of product quality control plans to be appropriate
for the conditioning purposes, on site inspections to control the quality of the waste form, checks of waste package inventory
declarations and accompanying waste package documentations with regard to the KONRAD specifications.
According to the Atomic Energy Act the German Federal States have to establish State Collecting Facilities (FSCS) for the
interim storage of the radioactive waste originating in their territories. The FSCFs deal in general with low active wastes arising in
nuclear medicine and at smaller research facilities (universities, industrial and health…
3) CENTRE DE LA MANCHE: A DISPOSAL FACILITY IN INSTITUTIONAL CONTROL (wP-59236)
Michel Dutzer, Jean Pierre Vervialle, Alain André, Albert Marchiol, Andra (France)
Centre de la Manche disposal facility is the first French surface disposal facility dedicated to low and intermediate level short
lived radioactive waste. It started up in 1969. After a continuous improvement, in the design of disposal vaults, in operational
modes, in the whole process of waste management, in the safety approach, the last packages were received in 1994. 527,000 m3 of
waste packages have been disposed during the 25 years of operation. The facility was licensed for the institutional control period
in 2003.
The disposal vaults are covered with a multilayer capping system that includes a bituminous membrane to provide protection
against rainwater infiltration. Water that might infiltrate through the membrane is collected by the bottom slab of the vaults to a
pipe network implemented in an underground gallery. Measurements show an overall infiltration rate of about 2.7 l/m2 /year that
complies with the objective of Andra of a few liters per square meter and per year.
Investigations are performed in order to assess the behavior of the membrane in the long term. For this purpose periodically
samples of the bituminous membrane are taken and measurements are performed.
As at the beginning of the operational period waste packages were not…
4) RADIOLOGICAL IMPACT OF CO-LOCATION OF THE VLLW AND
LILW REPOSITORY AT MOCHOVCE SITE (wP-59152)
Václav Hanusík, Zdena Kusovská, Jozef Morávek, VUJE, Inc.;
J. Balaz, O. Chren, Nuclear and Decommissioning Company plc. (Slovakia)
JAVYS, the Nuclear Decommissioning Company owner and operator of National Radioactive Waste Repository (NRR) at
Mochovce, is planning the enlargement of the existing NRR. The enlargement consists of the construction of new structures (double
rows) like the ones existing for LILW and of the new facility for the disposal of Very Low Level Waste (VLLW). A VLLW disposal
site is being planned in Mochovce where a LILW disposal site is already located. As a part of ongoing licensing process for
this change in utilization of the NRR we have updated the already existing assessment of potential radiological impact to members
of the public after closure of the site, both from the migration of leachate in groundwater from the site and from possible inadvertent
intrusion into the site, including future residence on the material excavated for the construction of the road. The radionuclides
from the ground water reach the biosphere through a spring flowing into the lake. It is conservatively assumed that individual in
the critical group uses biosphere of the lake (for irrigations, fishing and recreation). In the case of unintentional intrusion into the
repository, the exposed group consists of a small number of workers who excavate or examine repository
5) DEVELOPMENT OF AN ENGINEERING DESIGN PROCESS AND ASSOCIATED SYSTEMS
AND PROCEDURES FOR A UK GEOLOGICAL DISPOSAL FACILITY (wP-59160)
Philip Rendell, NDA; Henry O’Grady, Parsons Brinckerhoff: Brendan Breen, Alastair Clark, Steve Reece, NDA (UK)
In the United Kingdom the Nuclear Decommissioning Authority (NDA) has been charged with implementing Government policy
for the long-term management of higher activity radioactive waste. The UK Government is leading a site selection process
based on voluntarism and partnership with local communities interested in hosting such a facility and as set out in the Managing
Radioactive Waste Safely White Paper (2008).
The NDA has set up the Radioactive Waste Management Directorate (RWMD) as the body responsible for planning, building
and operating a geological disposal facility (GDF). RWMD will develop into a separately regulated Site Licence Company (SLC)
responsible for the construction, operation and closure of the facility. RWMD will be the Design Authority for the GDF; requiring
a formal process to ensure that the knowledge and integrity of the design is maintained.
In 2010 RWMD published Geological Disposal - Steps towards implementation which described the preparatory work that it
is undertaking in planning the future work programme, and the phases of work needed to deliver the programme. RWMD has now
developed a process for the design of the GDF to support this work. The engineering design process follows a staged approach,
encompassing options development, requirements definition, and conceptual and detailed…
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Abstracts Session 31
6) STATE OF THE ART FOR FABRICATING AND EMPLACING CONCRETE CONTAINERS INTO LARGE
HORIZONTAL DISPOSAL CAVERNS IN THE FRENCH GEOLOGICAL REPOSITORY (wP-59267)
Jean-Michel Bosgiraud, Maurice Guariso, François Pineau, Andra (France)
The research and development work presented in this paper was initialized by Andra in 2007. The work necessary for manufacturing
and testing a full scale demonstrator is presently implemented. The case story is twofold.
The first part is related to the initial development of a high performance concrete formulation used for fabricating concrete storage
containers (containing Medium Level and Long Lived Waste
primary canisters) to be stacked and emplaced into 400-m long concrete lined horizontal disposal vaults (also called caverns,
excavated in the Callovo-Oxfordian clay host formation at a 550 to 600-m depth) with an inside diameter of approximately 8-m.
The concrete formulation qualification process is described and the design and fabrication case story of the concrete boxes is
detailed. The rationale of the concept, the basics of its formulation and the technical achievements and performances obtained at
the end of the fabrication phase are described.
The second part presents the outcome at the end of the detailed design phase, for a system which is now being manufactured
(for further test and assembly) for the emplacement of the concrete containers inside the vault. The application was engineered for
remote emplacing a pile of 2 concrete containers (the containers are preliminarily…
7) ON-SITE, NEAR SURFACE DISPOSAL OF GRAPHITE WASTES IN THE UK (wP-59078)
Adam Meehan, Peter Sibley, EnergySolutions; Jeremy Lightfoot, Golder Associates (UK) Ltd.;
Duncan Jackson, Eden Nuclear & Environment Ltd., (UK)
Reactor graphite makes up about 30% by volume of the UKs inventory of intermediate level waste (ILW). There is estimated
to be about 15,000m3 of graphite arisings prior to 2040, mainly comprising operational waste streams (Magnox and AGR fuel
sleeves), along with core graphite from the decommissioning of experimental and prototype reactors. A further 65,000m3 of
graphite is forecast to arise after 2040, comprising core graphite from the final decommissioning of the Magnox and AGR reactors.
Consequently, the management and disposal of graphite wastes is of key strategic importance in the UK.
The current baseline strategy for reactor graphite wastes in the UK is to encapsulate them upon retrieval using a cementitious
grout in stainless steel Nirex containers in accordance with NDA Radioactive Waste Management Directorate (RWMD) Letter of
Compliance (LoC) specifications, and to dispose of them following a period of interim storage to the UKs planned geological disposal
facility (GDF), when this becomes available, currently planned for around 2040.
Using Magnoxs Hunterston A site as a Pathfinder, EnergySolutions and its partner organisations have been engaged with the
feasibility assessment, options assessment, engineering concept design and environmental safety case development for a proposed
on-site, near surface disposal facility for operational…
SESSION 31 — L/ILW WASTE CHARACTERIZATION, ASSAY, AND TRACKING SYSTEMS - PART 2 OF 2 (1.18)
1) NON-DESTRUCTIVE EXAMINATION OF TRU WASTE IN LOW AND HIGH DENSITY
BOXES AND DRUMS, USING HIGH ENERGY REAL TIME RADIOSCOPY (HE-RTR)
AND WIDE DYNAMIC RANGE IMAGING (wP-59302)
Stephen Halliwell, VJ Technologies Inc. (USA)
The Waste Isolation Pilot Plant (WIPP), the cornerstone of the Department of Energys nuclear waste cleanup effort, is designed
to permanently dispose of transuranic (TRU) radioactive waste. Real time radioscopy (RTR) using x-ray energies of up to 450keV,
has been used extensively for the non-destructive examination (NDE) part of the characterization and certification of waste drums
and low density waste boxes, prior to shipment to WIPP. However, to characterize drums and boxes containing a mixture of both
low and high density waste, x-ray energies of up to 6MeV, together with an x-ray imaging system having a wide dynamic range,
are required. The system, including the high energy vault, is required to be stand-alone, weatherproof and re-locatable, and must
be fully compliant with ANSI.N43.3, classified as an exempt shielded facility for x-ray energies up to 6MeV.
This paper describes the design, build and operation of the new generation of high energy RTR systems now being used in the
characterization of waste destined for disposal at WIPP.
Importance of this work. Characterization of TRU waste in boxes and drums by non-destructive examination reduces the need
to open the containment and to visually examine the waste. The immediate benefits are a reduction in risk of operator dose uptake,
a reduction in the generation of additional waste, and the saving of time and cost within the process.
2) MEASUREMENT METHODOLOGY FOR FULFILLING OF WASTE ACCEPTANCE CRITERIA
FOR LOW AND INTERMEDIATE LEVEL RADIOACTIVE WASTE IN STORAGES (wP-59016)
Marina Sokcic-Kostic, Felix Langer, Roland Schultheis, NUKEM Technologies GmbH (Germany)
Low level and intermediate level radioactive waste must be sorted and treated before it can be sent to radioactive waste storage.
A variety of parameters must be considered to fulfil the acceptance criteria for these storages. NUKEM Technologies has a
long time experience with the erection and management of radioactive waste treatment facilities and has developed methods and
equipment to produce the waste packages where all the required information are compiled.
The preferred methods are the non-destructive methods, which allow high throughput and give detailed information.
The required waste acceptance information is divided into physical, chemical and radiological aspects. Experience has shown
that different strategies have to be applied for their acquisition: the radiological information is acquired by measurements, whereas
the physical and chemical information is gathered from origin of waste, sorting and treatment procedures. In rare cases direct
measurements are applied in addition: the example for this is the grouting process.
The tracking data base system developed by NUKEM Technologies tracks the waste streams through the waste treatment facility
and combines the gathered information from the delivered waste to generate sophisticated waste declarations for further storage.
Physical and chemical parameters are managed via the tracking methodology, which has proven
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Session 31 Abstracts
3) DISPOSITION OF TRANSURANIC RESIDUES FROM PLUTONIUM ISENTROPIC COMPRESSION
EXPERIMENT (PU-ICE) CONDUCTED AT Z MACHINE (LA-UR-10-05649) (wP-59186)
Kapil K. Goyal, Los Alamos National Laboratory; Betty J. Humphrey, Weston Solutions Inc.; Jeffry Gluth, Ktech
Corporation/Sandia National Laboratory; David M. French, Los Alamos National Laboratory (USA)
In 1992, the U.S. Congress passed legislation to discontinue above- and below-ground testing of nuclear weapons. Because
of this, the U.S. Department of Energy (DOE) must rely on laboratory experiments and computer-based calculations to verify the
reliability of the nuclear stockpile. The Sandia National Laboratories/New Mexico (SNL/NM) Z machine was developed to support
the science-based approach for mimicking nuclear explosions and stockpile stewardship. Plutonium (Pu) isotopes with greater
than ninety-eight percent enrichment were used in the experiments. In May 2006, SNL/NM received authority that the Z Machine
Isentropic Compression Experiments could commence.
Los Alamos National Laboratory (LANL) provided the plutonium targets and loaded the target assemblies provided by
SNL/NM. Three experiments were conducted from May through July 2006. The residues from each experiment, which weighed
up to 913 pounds, were metallic and were packaged into a 55-gallon drum each.
SNL/NM conducts the experiments and provides temporary storage for the drums until shipment to LANL for final waste certification
for disposal at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. This paper presents a comprehensive
approach for documenting generator knowledge for characterization of waste in cooperation with scientists at the two laboratories
and addresses a variety of essential topics.
4) DETECTION OF SHIELDED SEALED RADIOACTIVE SOURCES IN RADIOACTIVE
WASTE BY NON-DESTRUCTIVE ASSAY TECHNIQUES (wP-59252)
Leo P.M. Velzen, Nuclear Research and Consultancy Group;
Steven van der Marck, Nuclear Research Group (Netherlands)
Experiences dealing with the detection of a SRS or its shielding in waste by non-destructive assay (NDA) methods are seldom
reported in literature. Therefore the main objective of this paper is to assist operators of waste storage facilities or others responsible
for the radiological characterisation of waste that they are able to interpret collected radiological data on the possible presence
of a bare SRS or a shielded SRS.
This objective can be reached by simulating the gamma flux that can be measured on the surface of a waste package containing
a bare or shielded SRS. Appropriate simulations and presentations of the results will illustrate the problems that can occur by
radiological data collection and interpretation in reality.
The simulating calculations have been performed with the Monte Carlo Neutron Photon transport code (MCNP) for gamma
photons of 60Co. Obtained results e.g. gamma and total energy flux are presented in iso-plots to help non-specialist operators interpreting
own collected radiological data to recognize a SRS and dense materials in (historic) waste packages.
The MCNP simulated waste packages have been defined to reflect, as close as possible, reality, i.e. the calculated data are disturbed,
as would be the situation in the case of raw…
5) USE OF LANTHANUM BROMIDE DETECTORS TO AUGMENT
SITE SURVEYS FOR DEPLETED URANIUM (w/P-59169)
Charles Waggoner, Mississippi State University; Ronald Unz, Institute for Clean Energy Technology;
Donna Rogers, Mississippi State University; Charles R. Jones,
Jay P. McCown, Institute for Clean Energy Technology/Mississippi State University (USA)
A variety of systems have now been described for use in surveying sites for anthropogenic radiological contamination. Virtually
all of these include use of sodium iodide detectors and register detection data with global positioning satellite data. This paper
demonstrates how lanthanum bromide detectors can be used to augment existing field surveys in a manner to reduce uncertainty in
areas of low count rates and to discriminate between depleted uranium and naturally occurring uranium.
The survey system described is equipped with large (20 x 20 x 100 cm) sodium iodide (Alpha Spectra) and 7.6 x 7.6 cm lanthanum
bromide (Saint Gobain) detectors. Additional radiological detection equipment (DigiBase) was obtained from ORTEC with
survey data collected in the List Mode. Data collected in surveys were then used to generate digital maps using GeoSofts Oasis
Montaj.
Software has been developed to automatically identify areas of increased count rates using user-defined thresholds. This software
can collect the count data for the masked area and generate a composite spectrum that can be compared to a reference spectrum
believed to represent an uncontaminated area. Ratios of counts attributed to protactinium-234m (Pa-234m) are compared to
counts attributed to Bismuth-214 (Bi-214) for both the composite filed survey spectrum…
6) ULTRASONIC TECHNIQUES FOR THE IN SITU CHARACTERISATION
OF ‘LEGACY’ WASTE SLUDGES & DISPERSIONS (wP-59111)
Timothy Hunter, Jeff Peakall, Simon Biggs, Michael Fairweather, James Young, University of Leeds, Leeds (UK)
Research being undertaken at the University of Leeds, as part of the DIAMOND university consortium, is exploring the effectiveness
of various ultrasonic technologies as in situ probes to characterize and monitor nuclear waste slurries, such as the Legacy
Magnesium hydroxide sludges found in Sellafield, U.K. Through use of a commercial Acoustic Backscatter Sensor (ABS) with 1
5 MHz transducers, various properties of free-settling oxide simulant sludges were determined. Work was focused upon characterizing
essentially static sludges (to give prospective use as tools for the wastes in current deposits); although, the sensors also have
potential as dispersion monitors during any future processing and storage of the Legacy wastes, as well as many other storage, clarifier
or thickener systems across a wide range of industrial processing operations.
ABS data of mixed glass powder dispersions was analysed and compared to scattering theory, to understand the correlations
between acoustic attenuation and particulate concentration. The ABS was also calibrated to measure changes in average particulate
concentration within a settling suspension over time, and showed the depth-wise segregation of the dispersion through the settling
column at different particular time intervals. It was found that observed hindered settling also led to an increase in particulate
concentration…
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Abstracts Session 32
7) FREE-RELEASE AND SORTING MONITORS DEVELOPED FOR NPP A-1
DECOMMISSIONING, SLOVAKIA (wP-59071)
Ondrej Slávik, VUJE; Alojz Slaninka, VUJE, a.s./ Slovak University of Technology in Bratislava;
Martin Liatjak, Kamil Kravárik, VUJE, a.s.; Igor Pély, JAVYS, a.s. (Slovakia)
Bohunice NPP A-1, Slovakia, was a pilot NPP shut down after nuclear accident with loss of fuel integrity in 1977. Presently,
the 2nd stage of decommissioning project implementation is carrying out. Within this stage of decommissioning it is necessary to
decontaminate, monitor and if possible to free release large amounts of contaminated materials. From point of view of the material
volume to be monitored, contaminated soil and concrete debris are the most crucial ones in this stage (thousands of tons). They
were until now temporary stored in underground basins or similar places within the NPP controlled area. Within the mentioned project
a pilot free-release and sorting monitoring post were developed in order to support the extended need to mentioned monitoring
capabilities.
The main goal expecting to the sorting monitor is to reduce the volume of contaminated materials to be monitored for freerelease.
An operative monitor was designed for this purpose that is based on quick and direct in situ measurements of loader spoon
filled with the excavated materials. A pair of NaI(Tl) detectors is used for the measurements. The spoon is fixed on a covered measurement
frame with automatic fixation logic (pair of rails and an inductive sensor on the…
8) DESIGN AND OPERATION OF THE COMBINED TECHNOLOGY AUTOMATED
WASTE CHARACTERISATION SYSTEM (wP- 59308)
John Mason, Marc R Looman, Robert A. Price, A. N. Technology Ltd. (UK)
This paper describes the design and operation of the Combined Technology Automated Waste Characterisation System (CTA-
WCS) at JRC Ispra. The 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. The WCS covers a range of activity including
Low and Intermediate Level Waste (LLW and ILW). The 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. The DDA performs conventional
passive neutron totals, coincidence, and multiplicity counting and active DDA total neutron counting. Data analysis is
based on the use…
SESSION 32 — REPOSITORY PROGRAMS: SITE SELECTION & CHARACTERIZATION,
UNDERGROUND RESEARCH LABS, ENGINEERING & GEOLOGICAL BARRIERS - PART 1 OF 2 (2.3)
1) SAFETY ASSESSMENT INPUT TO SITE SELECTION - THE SWEDISH EXAMPLE (wP-59031)
Johan Andersson, JA Streamflow AB (Sweden)
Svensk Kärnbränslehantering AB (SKB) has performed comprehensive investigations of two candidate sites for a final repository
for Swedens spent nuclear fuel; in Forsmark (municipality of Östhammar) and in Laxemar (municipality of Oskarshamn). In
March 2011 SKB decided to submit licence applications according to the Act on Nuclear Activities and the Environmental Code
for a final repository at Forsmark. The license applications include comprehensive documentation to support that a KBS-3 repository
at Forsmark will meet requirements in laws and regulations, including a full evaluation of long term safety. Before selection,
SKB stated that the site that offers the best prospects for achieving long-term safety in practice would be selected. Based on experiences
previous safety assessments, a number of issues related to long-term safety need to be considered in the context of site comparison.
The factors include sensitivity to climate change such as periods of permafrost and glaciations, rock mechanics evolution
including the potential for thermally induced spalling and sensitivity to potential future earthquakes, current and future groundwater
flow, evolution of groundwater composition and proximity to mineral resources. Each of these factors related to long-term safety
for the two candidate sites is assessed in a comparative analysis of site characteristics. The assessment ...
2) TECHNICAL KNOW-HOW OF SELECTION PROCESS FOR THE HORONOBE
UNDERGROUND RESEARCH LABORATORY AREA AND SITE (wP-59088)
Takanori Kunimaru, Ryuji Takeuchi, Tatsuji Matsuzaki, Japan Atomic Energy Agency (Japan)
The Horonobe Underground Research Laboratory (URL) Project is being pursued by the Japan Atomic Energy Agency (JAEA)
to enhance the reliability of relevant disposal technologies through investigations of the deep geological environment within the
host sedimentary formations at Horonobe, northern Hokkaido, Japan. The project consists of two major research areas, Geoscientific
Research and R&D on Geological Disposal, and proceeds in three overlapping phases, Phase I: Surface-based investigation
Phase, Phase II: Construction Phase and Phase III: Operation Phase, over a period of 20 years.
The early Phase I of the Horonobe URL project consisted of selecting a URL area and URL site, which involved establishing
fundamental factors relating to the geological environment and safety, surface-based investigations of the geological environment,
stepwise narrowing down of candidate or target areas (sites) from the whole Horonobe Town area through candidate URL areas
and, finally, to a URL site.
This study will be demonstrated the selection process for the URL area and URL site in sequence. Horonobe URL has been
declared to be constructed within whole Horonobe Town to be selected early in the fiscal year 2002. The Horonobe URL area/site
is required existence of host argillaceous sedimentary formations and saline groundwater. Further fundamental requirements ...
95

Session 32 Abstracts
3) CHARACTERISATION OF BEDROCK HYDROGEOLOGY AT THE OLKILUOTO
SITE USING SURFACE BASED AND UNDERGROUND DATA (w/oP-59095)
Lee Hartley, Dave Swan, Steven Baxter, SERCO (UK)
Posiva Oy is responsible for implementing the programme for geological disposal of spent nuclear fuel in Finland. Olkiluoto
in Eurajoki has been selected as the primary site for the repository, subject to further detailed characterisation which is currently
focused on the construction of an underground rock characterisation and research facility (the ONKALO). An essential part of the
site investigation programme is analysis of groundwater flow and solute transport to depth by means of numerical flow modelling
as part of the 2011 site descriptive model. Groundwater flow in the crystalline rocks at Olkiluoto takes place predominantly in the
void space of the interconnected fractures in the bedrock. Many of the hydraulic characteristics of flow through such a system can
be represented by hydrogeological Discrete Fracture Network (DFN) models, since they capture some of the details of fracture
geometry, size, connectivity and openings. The paper describes how field data is used to derive such models, ultimately for use in
safety assessment.
Surface based site investigations at Olkiluoto include 53 sub-vertical deep core drilled boreholes and 27 shallower sub-vertical
boreholes. The characterisation of fractures is a key objective. Fracture geometrical data (fracture positions and orientations)
are determined from drill core mapping and/or borehole ...
4) SELF-DISPOSAL OPTION FOR HEAT-GENERATING WASTE (wP-59182)
Michael Ojovan, University of Sheffield; Pavel Poluektov, Vladimir Kascheev, A.A. Bochvar’s VNIINM (UK/Russia)
Self-descending heat generating capsules can be used for disposal of dangerous radioactive wastes in extremely deep layers of
the Earth preventing any release of radionuclides into the biosphere. Self-disposal option for heat-generating radioactive waste such
as spent fuel, high level reprocessing waste or spent sealed radioactive sources, known also as rock melting concept, was considered
in the 70s as a viable alternative disposal option by both Department of Energy in the USA and Atomic Industry Ministry in
the USSR. Self-disposal is currently reconsidered as a potential alternative route to existing options for solving the nuclear waste
problem and is associated with the renaissance of nuclear industry. Self-disposal option utilises the heat generated by decaying
radionuclides of radioactive waste inside a heavy and durable capsule to melt the rock on its way down. As the heat from radionuclides
within the capsule partly melts the enclosing rock, the relatively low viscosity and density of the silicate melt allow capsule
to be displaced upwards past the heavier capsule as it sinks. Eventually the melt cools and solidifies (e.g. vitrifies or crystallizes),
sealing the route along which the capsule passed. Descending or self-disposal continues until enough heat is generated by radionuclides
to provide partial ...
5) NUMOS APPROACH FOR LONG-TERM SAFETY ASSESSMENT (wP-59404)
Takeshi Ebashi, Kenichi Kaku, Katsuhiko Ishiguro, Nuclear Waste Management Organization of Japan (NUMO) (Japan)
In Japan, the Act on Final Disposal of Specified Radioactive Waste specifies that the repository siting process shall consist of
three stages. The Nuclear Waste Management Organization of Japan (NUMO) is responsible for geological disposal of vitrified
high-level waste and some types of TRU waste. NUMO has chosen to implement a volunteer approach to siting.
NUMO decided to prepare the 2010 Technical Report, which sets out three policies for ensuring safety. One of these is staged
project implementation and decision-making based on iterative confirmation of safety. Based on this, NUMO will gradually integrate
relevant interdisciplinary knowledge to build a safety case once a formal volunteer application is received that would allow
site investigations to be initiated. The safety assessment takes the central role in multiple lines of reasoning and argumentation by
providing a quantitative evaluation of long-term safety, a key aspect of which is uncertainty management.
This paper presents NUMOs basic strategy for long-term safety assessment, based on the above policy.
In concrete terms, safety assessment procedures are described in the context of the staged implementation programme, based
on integration of knowledge obtained from site investigation/evaluation and engineering studies and reflection of the safety assessment
results in the planning of ...
6) MODELING APPROACHES FOR EVALUATING THE EFFECT OF HETEROGENEITY ON
TWO-PHASE FLOW ASSOCIATED WITH THE MIGRATION OF WASTE GENERATED GAS
FROM SF/HLW- AND L/ILW REPOSITORIES IN LOW-PERMEABILITY FORMATIONS (wP-59196)
Alexandros Papafotiou, Rainer Senger, Intera Inc. Swiss Branch; Andrés Alcolea, TK Consult AG;
William Lanyon, Fracture-Systems Ltd; John Ewing, Intera Inc. Swiss Branch (Switzerland/UK)
Different low-permeability formations are considered as potential host rocks for Low / Intermediate Level waste (L/ILW) and
spent fuel / high-level / long-lived intermediate-level waste (SF/HLW/ILW) in Switzerland. As part of a generic site evaluation
process, emphasis is on the assessment of Mesozoic limestones, marls and claystones in six potential siting areas in Northern and
Central Switzerland. An important aspect in the site evaluation process is the characterization of the low-permeability formations
in terms of spatial variability of the relevant transport properties (porosity, permeability, clay content), as they may affect the migration
of waste-generated gas from L/ILW and SF/HLW/ILW repositories.
Numerical modeling studies are presented, aimed at quantifying the impact of spatial variability of rock properties on gas
release through the host rock on a deca- to hectometer scale. For this purpose, 2-D models of an emplacement tunnel embedded in
a low-permeability host rock are developed for both a sequence of limestones and marls with distinct lithological variability (Effingen
Beds) and a claystone of moderate spatial variability (Opalinus Clay). For the Effingen Beds, a composite geological model is
implemented, comprising stochastic representations of the different facies and the fracture systems. The facies model displays spatial
variations in clay content, porosity ...
96

Abstracts Session
7) A NEW SAFETY CONCEPT FOR GEOLOGICAL DISPOSAL IN JAPAN (II) (wP-59357)
Kazumi Kitayama, Nuclear Waste Management Organization of Japan (NUMO) (Japan)
In a previous paper for ICEM2009 a new safety concept was proposed for the geological disposal program in Japan, which was
a development of the conventional multi-barrier system concept that takes greater account of the actual behaviour in a deep geological
environment. This paper describes progress of the study. In particular, it points out that geological disposal provides passive
defence-in-depth safety functions based on geochemical equilibrium, and that natural analogues are effective in understanding the
behaviour of engineered/natural barriers over hundreds of thousands of years and in further developing safety concepts. In addition,
a long-term safety concept based on the realistic evolution of a geological disposal system can be explained to both the general
public and experts in a straightforward and comprehensible manner.
Detailed discussion of specific long-term behaviour of engineered and natural barriers, including possible interaction between
barriers, will be reported in the paper.
8) THERMO-HYDRO-MECHANICAL SIMULATION OF A HEATING AND HYDRATION
EXPERIMENTAL STUDY (CHINA-MOCK-UP) IN UNSATURATED GMZ BENTONITE (wP-59212)
Liang Chen, Ju Wang, Yuemiao Liu, Beijing Research Institute Of Uranium Geology;
Federic Collin, University Of Liège; Jingli Xie, Beijing Research Institute Of Uranium Geology (China/Belgium)
The preliminary repository concept for disposal of high level radioactive waste in China is a shaft-tunnel model, located in saturated
zones in granite. The engineered barrier system (EBS) is composed of vitrified waste, canisters, buffer materials, backfill
and seals. Unsaturated compacted bentonite is foreseen by lots of countries as a backfill and sealing material. At the present stage,
the Gaomiaozi (GMZ) bentonite is considered as the candidate buffer and backfill material for the Chinese repository. In order to
study the behavior of this material in coupled THMC conditions, a mock-up facility, named China-Mock-up, has been installed in
Beijing Research Institute of Uranium Geology. The heater, which substitutes a loaded waste canister, is placed inside of the facility.
To simulate the impact of groundwater, the water inflow of the barrier from outer surface is also possible. This paper presents
a numerical study of the coupled THM behavior of China-mock-up test. In the paper, the basic physical characters of GMZ bentonite
and experimental facility of China-mock-up test are firstly presented. Based on the experimental studies, the numerical simulation
is realized by the program of LAGAMINE. In the simulation, the following physical phenomena are taken account: the
transport of liquid (advection) and heat ...
SESSION 33 — RECENT ADVANCES IN PROCESSING AND IMMBOLIZATION OF HLW,
FISSLE MATERIAL AND TRANSUANIC (TRU) - PART 1 OF 2 (2.14)
1) URANIUM METAL OXIDATION, GRINDING AND ENCAPSULATION IN BOROBOND:
TRU WASTE MANAGEMENT (w/oP-59279)
Kevin Cook, Larry Addington, Beth Utley, Boron Products (USA)
Hydrogen generation mitigation for K Basin sludge was examined by encapsulation of uranium metal in BoroBond®, pre-oxidation
of uranium metal with Fentons reagent and grinding of Densalloy SD170, an irradiated uranium metal surrogate. Encapsulation
in BoroBond® resulted in pressure increase rates at 60°C ranging from 0.116 torr/h to 0.186 torr/h compared to 0.240 torr/h
for a uranium metal in water standard. Samples cast with higher water content led to increased rates. A Fentons reagent system
consisting of a simple reagent mix of FeSO4•7H2O, H2O2 and HCl effectively oxidized ¼ cubes of uranium metal in under four
days at room temperature. Increased peroxide addition rate, increased FeSO4•7H2O concentration and low pH all increase the corrosion
rate. Densalloy SD170 with an average particle size of 581 µm with 7.63 % of particles less than 90 µm was milled so that
over 90 % of the Densalloy mass measured less than 90 µm in 6 hours of milling. Acceptable wear rates were seen on wear components
that were from standard materials (Nitronic SS and 440SS).
2) RESULTS OF INVESTIGATION OF HIGH LEVEL SOLID RADIOACTIVE WASTE
FROM PITS NO1 AND NO2 AT THE GREMIKHA SITE (w/oP-59390)
B.S. Stepennov, V.M. Afanasyev, A.Yu. Kazennov, N.V. Kartashev, A.V. Korolev, O.E. Kiknadze, D.V. Pavlov, Kurchatov
Institute; V.V. Eremenko, FGUP SevRAO; G. Fady, CEA; Lucien Pillette-Cousin, Areva TA (Russia/France)
One of the legacies of the Cold War period is the unsafe and uncontrolled storage of high level radioactive waste at the former
soviet navy bases. At the former naval maintenance base of Gremikha in the North-West of Russia, it has been necessary to conduct
characterization of high level waste in order to decide the best way to recover and condition it, with good radiation protection
and safety conditions. France, represented by CEA, associated with AREVA TA as technical support, funded the studies performed
by the Russian partners to define conditions of characterization of this high level waste that has been stored for tens of years in two
pits, filled with water and containing sludge. The Russian Kurchatov Institute conducted the clarification of the water contained in
the pit by removal of sludge using filtration techniques. Then, a 3D model of the content of the pits was realized including all
objects identified after water clarification. Specific methods and technologies were used for that because the dose rates near some
objects were as high as 400 Gy/h. Data obtained makes it possible now to choose the best option for the management of the identified
high level solid radioactive waste. The paper presents the techniques used for clarification of water contained in the pits, the
main results and the expected way forward to recover and condition this high level waste.
97

Session 34 Abstracts
3) PILOT TEST OF PRECIPITATION SETUP FOR DUST SUPRESSOR AND TRANSURANIC ELEMENTS
REMOVAL FROM WASTEWATERS OF CHERNOBYL NUCLEAR POWER PLANT (w/oP-59256)
Valentin Avramenko, Svetlana Bratskaya, Dmitry Marinin, Institute of Chemistry FEBRAS; Anatoliy Terzi,
Mariya Yarmolyuk, Chernobyl Nuclear Power Plant (Russia/Ukraine)
In this paper we report the results of pilot tests of flocculation/precipitation setup for dust-suppressor (DS) and transuranic elements
(TRU) removal from wastewaters of Chernobyl Nuclear Power Plant (ChNPP), including those of the Object Shelter . Tests
were performed on the pilot unit (PU), which included service tank, precipitation tank, and accumulation tank, 300 dm3 each, connected
with pipelines with dosing and pumping equipment, and throttle valves providing controlled dosing, mixing, precipitation
and mechanical filtration of radioactive wastewaters under different conditions. Three samples of the wastewaters drainage waters
from the Object Shelter , combined drainage waters of Object Shelter and 3rd reactor unit of ChNPP, and evaporator concentrate
from SVO unit of ChNPP were tested. The reagent compositions used in pilot tests were based on coagulant POLYPACS-30 LF
(aluminum polyoxychloride), synthetic cationic flocculants Besfloc K6634, K510CA, K6732 («Kolon Life Science, Inc», South
Korea) varying in molecular weight and charge density, and natural cationic flocculant «Chitofloc» (Institute of Chemistry
FEBRAS, Russia). The following wastewater parameters were controlled during the pilot tests: pH, dry residue, oxygen consumption,
total alpha- and beta-activity, isotope composition, optical density and DS content.
It was shown that wastewaters with DS content of 200-300 mg/L could be effectively…
4) SEPARATION PROCESSES FOR THE PRETREATMENT OF HIGH-LEVEL NUCLEAR
WASTES AT THE SAVANNAH RIVER SITE (w/oP-59291)
David Hobbs, Aiken, Thomas Peters, Kathryn Taylor-Pashow, Fernando Fondeur, Charles Nash, Samuel Fink,
David Herman, Savannah River National Laboratory (SRNL) (USA) Presentation by: Jim Marra, US DOE (USA)
Separation methods for the pretreatment of the high-level nuclear wastes (HLW) at the Savannah River Site (SRS) include the
Caustic Side Solvent Extraction (CSSX) process for cesium and adsorption/ion exchange for the removal of cesium, strontium and
alpha-emitting actinides. The CSSX process 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 Pu-238, Pu-239, Pu-240 and Np-237). 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. The same separation processes are also planned
for the much larger Salt Waste Processing Facility (SWPF). The SWPF, which has a design throughput of about 27 million liters
per year, is under construction and scheduled to begin radioactive operations in 2014.
Current R&D activities for the CSSX process are focused on implementing a new solvent system and stripping flowsheet that
offers enhanced extraction and stripping of cesium. This next generation solvent system features a different calixarene extractant,
uses caustic instead of nitric…
SESSION 34 — URANIUM SITES, ER ISSUES, SITE CHARACTERIZATION
AND MONITORING - PART 2 OF 2 (4.12) (4-6)
1) SAMPLING IN DECOMMISSIONING: CETAMA SEMINAR AND INTERNATIONAL OVERVIEW (w/oP-59209)
Guy Granier, Daniele Roudil, CEA MARCOULE; Didier Dubot, CEA/FAR/USLT/SPRE/SAS (France)
The quality of measurement is crucial for the safety of nuclear facilities and is a primary requirement for the characterization
of nuclear materials, fissile material monitoring and accountancy.
The Commission for the Establishment of Analysis Methods (CETAMA) is a unit of the French Alternative Energies and Atomic
Energy Commission (CEA) set up to improve the quality of analysis and measurement results, in the nuclear field, by proposing
suitable scientific and technical developments:
• Preparation and/or certification or reference materials;
• Organization of interlaboratory comparisons to assess the quality of the results and to validate analysis methods
• Published methods and reference documents validated by laboratory experiment
• Organization of workshops to share the reporting of experience among analysts
To ensure, at each level of its exploitation, a control of nuclear material dissemination is a main priority of nuclear industry in
France. Analysis is the main tool of supervision to follow this goal.
By the choice of adapted tracers, with definite frequencies the analysis allows a control and a follow-up of the nuclear operation
of the installations.
For more than 50 years of uninterrupted evolution this industry developed the comprehensive view about different aspects,
civil, military, production of energy or medical…
2) FOAM NOVEL DELIVERY TECHNOLOGY FOR REMEDIATION
OF VADOSE ZONE ENVIRONMENTS (wP-59019)
Dawn Wellman, Danielle P Jansik, Shas Mattigod, Lirong Zhong, Pacific Northwest National Laboratory;
Yuxin Wu, Lawrence Berkeley National Lab; Martin Foote, MSE Technology Applications;
Z. F. (Fred) Zhang, Pacific Northwest National Laboratory; Susan Hubbard, Lawrence Berkeley National Lab (USA)
Deep vadose zone environments can be a primary source and pathway for contaminant migration to groundwater. These environments
present unique characterization and remediation challenges that necessitate scrutiny and research. The thickness, depth,
and intricacies of the deep vadose zone, combined with a lack of understanding of the key subsurface processes (e.g., biogeochemical
and hydrologic) affecting contaminant migration, make it difficult to create validated conceptual and predictive models of subsurface
flow dynamics and contaminant behavior across multiple scales. These factors also make it difficult to design and deploy
sustainable remedial approaches and monitor long-term contaminant behavior after remedial actions.
98

Abstracts Session 35
Functionally, the methods for addressing contamination must remove and/or reduce transport of contaminants. This problem
is particularly challenging in the arid western United States where the vadose zone is hundreds of feet thick, rendering transitional
excavation methods exceedingly costly and ineffective. Delivery of remedial amendments is one of the most challenging and critical
aspects for all remedy-based approaches. The conventional approach for delivery is through injection of aqueous remedial solutions.
However, heterogeneous deep vadose zone environments present hydrologic and geochemical challenges which limit the
effectiveness. Because the flow of solution infiltration is dominantly controlled by gravity and suction, injected liquid preferentially
percolates…
3) MOBILITY OF RADIUM FROM PYRITIC URANIUM MINE TAILINGS UNDER
SUB-AQUEOUS DISPOSAL CONDITIONS (wP-59283)
Nand Dave, Mining and Mineral Sciences Laboratories Canada (Canada)
All uranium mines in the Elliot Lake uranium mining district of north-central Ontario, Canada, have been closed due to low
ore grade and prevailing market conditions. A majority of the waste management facilities have been rehabilitated and decommissioned
with in-situ shallow water covers to minimize sulphide oxidation, and hence acid generation and release of metal enriched
effluents.
Laboratory lysimeter investigations were undertaken to evaluate the leaching characteristics and mobility of Ra-226 and other
heavy metals (U, Th and Pb) from pyritic uranium mine tailings under sub-aqueous disposal conditions for assessing the long-term
radiological stability of such waste repositories. The experiments were conducted using three types of un-oxidized tailings: coarse,
fine and gypsum depleted mill total tailings. Shallow water covers of depth ~ 0. 3 m were established using natural lake water. The
leaching characteristics of radium and other major and trace metals were determined by monitoring both surface and pore water
qualities as a function of time.
The results showed that Ra-226 is leached from surface of the submerged tailings and released to both surface water and shallow
zone pore water during initial low sulphate ion concentration of the surface water cover in all three cases. The release of Ra-
226…
4) REMEDIATION PROJECT PLANNING AT THE URANIUM PRODUCTION LEGACY SITES.
LESSON LEARNED FROM THE BEST INTERNATIONAL PRACTICE AND CHALLENGES
FOR DEVELOPING COUNTRIES (wP-59043)
Oleg Voitsekhovych, Ukrainian Hydrometeorological Institute (Ukraine)
The former Soviet Union countries such as Kazakhstan, Kyrgyzstan, Russia, Tajikistan, Uzbekistan and Ukraine, where uranium
production legacy sites are located (such as mines, waste rock piles, pits, chemical and hydrometallurgical plants, tailing
dumps, etc.) are currently facing the challenge of making these objects environmentally safe. These countries share a common history
of the uranium mining and milling industry, similar regulatory shortcomings and uncertainties regarding the strategy justification
for such remediation projects. They also have to deal with scarcity of financial resources for long-term remediation programmes,
and lack of experience with planning and management of environmental remediation projects at former uranium production
sites.
In the recent years, IAEA-supported programmes of international technical co-operation (the projects RER/0986 and
RER/3010) were advancing actively, as well as those sponsored by the UNDP, EurAsEC and others, all aiming to assist with the
preparedness and performance of future remediation projects. As demonstrated by analysis, effectiveness of the many programmes
largely depends on the nations’ level of preparedness to carry out remediation projects in accordance with the international standards.
The lessons learned from analyses of the different type of projects, which were already implemented or which are still in plan
in different countries and in particular…
5) CLOSE-OUT OF OPEN PIT AND WASTE ROCK PILES OF DAXIN URANIUM MINE OF CHINA (wP-59073)
Lechang Xu, Changshun Ren, Min Shi, Liaoning Xueli Zhang,
Jie Gao, Beijing Research Institute of Chemical Engineering and Metallurgy, CNNC (China)
Daxin Uranium Mine is an small open pit mine. Its contaminated facilities include open pit 87620m2 , East waste rock pile
71710m2 , west waste rock pile 57828m2 , ore transfer station and industrial fields 9370m2 , building and structure 26600m2 , equipment
246 pieces, plastic conduit 3000m. steel conduit 2500m2 and road for transporting ores 1020m. The integrated decommissioning
programmes are presented: uranium extraction, slope stabilization, clear-up, backfill, reshape, covering, re-vegetation, dismantlement/demolishment,
decontamination, re-smelting, waste water treatment.
SESSION 35 — (MERGED WITH SESSION 34)
SESSION 36 — RADIUM REMEDIATION: HISTORICAL PERSPECTIVES
AND CURRENT CIRCUMSTANCES - PART 1 OF 3 (4.11)
1) RADIUM DIAGNOSIS CAMPAIGN (wP-59327)
Florence Gabillaud-Poillion, Autorité de Sûreté Nucléaire (France)
In line with the approaches already adopted in France during the 90s on various sites where research and/or radium-extraction
activities were mostly conducted in the past, the French public authorities wish from now on to pursue their prevention and siterehabilitation
approach inherited from the French craftsman and medical sectors that used that radioelement.
As a matter of fact, radium has been in use in several medical activities, notably in the initial methods of cancer therapy. Similarly,
it was also used in some craftsman activities, such as the clock industry, for its radioluminescent properties, the fabrication
of lightning conductors or cosmetics until the 60s. Those activities have generated various traces of pollution that have remained
today.
99

Session 36 Abstracts
On the basis of the different inventories of industrial sites where radium may have been held or used, and notably the inventory
updated by the French Institute for Radiation Protection and Nuclear Safety (Institut de radioprotection et de sûreté nucléaire
IRSN) in 2007 at the request of the French Nuclear Safety Authority (Autorité de sûreté nucléaire ASN), French State services
have potentially identified 134 sites that hosted radium-related activities in France. The radiological status of those sites is either
unknown or very partially…
2) ANDRA’S REMEDIATION MISSIONS (w/oP-59210)
Patrick Poiret, Eric Lanes, Andra (France)
For many years now, the French National Radioactive Waste Management Agency (Agence nationale pour la gestion des
déchets radioactifs Andra) has been cleaning up several sites contaminated with radioactivity, bearing in mind that all such remediation
missions share the unique peculiarity of being performed entirely outside the nuclear-power-generation field.
Thanks to the 2006 Planning Act and the new corporate circular in the legal field, to the implementation of the CNAR for
organisational purposes, to the public technical subsidy for dedicated storage facilities and the disposal facility for VLL waste (Centre
TFA) from a financial standpoint, Andras new structure is now in place to ensure a proactive approach to manage the environmental
liabilities arising from the sites polluted by radioactive materials, which, although scarce in number, each confront us with
a specific challenge.
3) URANIUM MILL TAILINGS REMEDIATION IN THE USA. A HISTORY AND LESSONS LEARNED (w/oP-59407)
Steve Rima, AMEC (USA)
Since the 1940s uranium ores have been processed at various locations in the United States to extract and produce uranium and
other concentrated materials, first for government (weapons) research and production, and then for nuclear power production. The
tailings residue from the uranium milling process contained radioactive (primarily Ra-226) and hazardous chemicals. Large volumes
of tailings were produced during the milling process. In the early history of this process the tailings were not recognized as
hazardous and were released to the general public for a wide variety of uses, resulting in significant spread of contamination in the
vicinity of many operating mills.
In the late 1960s and early 1970s laws were enacted at the state and federal level to begin to deal with the legacy of this contamination.
Over the course of the next several decades various regulatory agencies were responsible for remediating these sites.
Different approaches were used, different end points and definitions of clean were used, and very large sums of public funding were
spent on remediating these sites. Rarely was the cost commensurate with the risk reduction obtained through remediation.
This paper will present an overview of the history of the uranium mill tailings regulatory and remediation program in the United
States, the cost of the program compared to risk reduction, successes and failures, and important lessons learned that should be
applied to future efforts in this area.
4) REMEDIATION OF CANADA’S HISTORIC HAUL ROUTE FOR RADIUM AND
URANIUM ORES: THE NORTHERN TRANSPORTATION ROUTE (wP-59303)
Robert Brian Geddes, Chris Wenzel, AMEC; Michael Owen,
Mark J. Gardiner, AECL; Julie Brown, Natural Resources Canada’s (Canada)
Established in the 1930s, the Northern Transportation Route (NTR) served to transport pitchblende ore 2,200km from the Port
Radium Mine in Canadas Northwest Territories to Fort McMurray in Alberta. From there, the ore was shipped 3,000km by rail to
the town of Port Hope, Ontario where it was refined for its radium content and used for medical purposes. Later, refinement
focussed on uranium content.
The corridor of lakes, rivers, portages and roads that made up the NTR included a number of transfer points, where ore was
unloaded and transferred to other barges or trucks. Ore was occasionally spilled during these transfer operations and, in some cases,
subsequently distributed over larger areas as properties were re-developed or modified. In addition, relatively small volumes of ore
were sometimes transported by air to the south.
Since 1992, the Low-Level Radioactive Waste Management Office (LLRWMO) has conducted surveys to identify and characterize
spill sites along the NTR where soils exhibit elevated concentrations of uranium, radium and/or arsenic. In addition to significant
areas of impact in Fort McMurray, contamination along the NTR was centred in the Sahtu region near Great Bear Lake and
along the southern part of the Slave River. Early radiological investigations found…
SESSION 37 — YOUNG GENERATION NETWORK (YGN) AND
PROFESSIONAL DEVELOPMENT PROGRAMS (5.16)
1) THE REESTABLISHMENT OF RADIOCHEMISTRY ACADEMIC
PROGRAMS IN THE UNITED STATES (w/oP-59025)
Craig Williamson, South Carolina Universities Research and Education Foundation (USA)
Despite its importance in national security, medicine, energy, and in waste management radiochemistry education in the United
States has gone through two lost decades. In the 1970s ten to fifteen universities were granting between thirty (30) and forty (40)
doctoral degrees a year. By the 1980s those numbers had declined to twenty (20) and thirty (30) a year, by the 1990s the numbers
had again decreased to below fifteen (15) Ph.D.s a year. In the year 2000, the data shows that only 5 Ph.D.s in radiochemistry were
awarded. The causes for this decline is directly attributed to the lack of federal support for an academic discipline that for the most
part depends on federal funding.
In 2011, it is expected that over thirty (30) doctoral degrees in radiochemistry will be conferred. The turn around in radiochemistry
education in the United States can be directly attributed to the support provided by the U.S. Departments of Energy, Defense
and Homeland Security. In addition, support has come from the U.S. Nuclear Regulatory Commission and from the National
Nuclear Security Administration. The form of this support has been extensive from proposed undergraduate research programs,
scholarships, graduate fellowships, junior faculty awards, curriculum awards, and grants…
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2) PLANNING FOR DECOMMISSIONING OF NUCLEAR FACILITIES -
THE VIEWS OF YOUNGER STAKEHOLDERS (wP-59222)
Staffan Lindskog, Swedísh Radiation Safety Authority;
Bea Labor, Badania Dydaktycne Project 2010 (Sweden/Poland) (Final paper received and Copyrights pending)
Title: Nuclear as a semi-sustainable energy source the views of younger stakeholders
It is planned that many nuclear facilities will be decommissioned in the near future. This challenge includes certified repositories
for LLW and ILW, procedures for classification and free release, systems for transportation, planning activities, and liaison with
the public. The last item can have a substantial impact on the efficiency of decommissioning projects. Insufficient dialogue with
various stakeholder groups can be a factor that drives costs, whilst appropriate programs, means and environments for communication
and knowledge transfer may facilitate the establishment of contemporary and comprehensive bases for decisions and thereby
also enhance the possibility for consensus and thereby achieve feasible and sustainable solutions. The programs thus decided for
the decommissioning of nuclear facilities and the management of the nuclear waste must then be communicated openly and constitute
an integral part of the stakeholder related activities.
The nuclear renaissance implies as well as calls for newer platforms for communications with the stakeholders. This communication
must include how compliance with the Polluter Pays Principle (PPP) (and also preferably the Extended Polluter Responsibility,
EPR) is to be achieved, i. e. how the generation harvesting the benefits from nuclear electricity will…
3) GRADUATE OR APPRENTICE? HOW NUCLEAR TRAINING PROVISION HAS CHANGED
THE SHAPE OF THE NUCLEAR EMPLOYMENT MARKET (w/oP- 59415)
Corhyn Parr, Nuclear Enterprise (UK)
ABSTRACT NOT AVAILABLE
4) NUCLEAR KNOWLEDGE DEVELOPMENT - OVERVIEW OF THE ACTIVITIES
PROPOSED BY SFEN YOUNG GENERATION (SFEN-JG)
Guillaume Vaast, SGN–Pierrelatte (France)
ABSTRACT NOT AVAILABLE
SESSION 38 — MEETING: YOUNG GENERATION NETWORK (YGN)
AND PROFESSIONAL DEVELOPMENT PROGRAMS (5.17)
ABSTRACT NOT AVAILABLE
SESSION 39A — POSTER SESSION: FACILITY DECONTAMINATION AND DECOMMISSIONING
A-1) USE OF HIGHLY PRESURIZED LIQUID NITROGEN TECHNOLOGY FOR CONCRETE
SCABBLING APPLICATION AT SICN NUCLEAR FACILITIY (wP-59282)
Fabrice Moggia, Claire-Emilie Vaudey, Thierry Varet, Valérie Toulemonde, AREVA;
Frédéric Richard, Air Liquide CTAS; Gary Anderson, Nitrocision; Frédérique Damerval, AREVA (France/USA)
Dismantling and decommissioning (D&D) operations of nuclear site facilities usually involve the implementation of a large
number of technologies. These technologies are mostly dedicated to decontamination, cutting and concrete scabbling operations.
Technologies used for example for concrete scabbling are: disk sander, bush hammer, water jet, planer & Such mechanicals processes
proved to work since facilities are being decommissioned; however as larger projects are foreseen, the capability of such applications
to fulfill the requirement in term of economics, techniques and environment/social remains uncertain. Indeed, the efficiency
and the speed rate remains low, many operators are required to operate, implying a high dosimetry, the working conditions are
strenuous and finally the operations could last several years for large surfaces&
For all these reasons, it seems necessary to search for new technologies, which would bring sustainability to the D&D operations
while carrying a higher standard in terms of safety, easiness and economic value.
The Nitrojet technology is a process able to produce liquid nitrogen at low temperature and very high pressure (up to 4000
bar). Liquid nitrogen is collected from a tank to be pressurized in a specific skid. The nitrogen stream can then be applied on the
substrate
The use of this new…
A-2) METHODOLOGY OF EXTERNAL EXPOSURE CALCULATION FOR REUSE OF
CONDITIONAL RELEASED MATERIALS FROM DECOMMISSIONING (wP-59138)
Frantisek Ondra, Marek Vaako, DECOM, a.s.; Vladimir Necas, Slovak University of Technology (Slovakia)
Conditional release of materials is a part of nuclear installation decommissioning that can significantly influenced radioactive
waste management, radioactive waste repository capacity usage as well as total decommissioning cost. For performance of conditional
released materials scenarios it is needed to determine radiological, material, organizational and other conditions for conditionally
released materials reuse to not breach exposure limits for staff and public during scenarios life cycle (preparation, construction
and operation of scenario). The article presents a methodology for determination of above mentioned conditions to ensure that
staff and public exposure does not breach the limits. The methodology comprises a proposal of following conditions in the view of
staff and public exposure:
• radionuclide limit concentration of conditionally released materials for specific scenarios and nuclide vectors,
• specific deployment of conditionally released materials eventually shielding materials, staff and public during the scenarios
life cycle,
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Session 39 Abstracts
“ organizational measures concerning time of staffs or publics stay in the vicinity on conditionally released materials for
individual performed scenarios and nuclide vectors.
The article further describes VISIPLAN 3D ALARA calculation planning software tool, having been used for calculation of
staffs and publics external exposure for individual scenarios. Several other parallel papers proposed for ICEM 11 are presenting
selected details of the project.
A-3) UNCERTAINTY ANALYSIS OF ACTIVITY MEASUREMENT OF NEW MONITORING SYSTEM
FOR FREE-RELEASE FOR NPP A-1 DECOMMISSIONING, SLOVAKIA (wP-59244)
Alojz Slaninka, VUJE, a.s./ Slovak University of Technology in Bratislava; Ondrej Slávik, VUJE, a.s.;
Vladimir Necas, Slovak University of Technology (Slovakia)
Within 2nd stage of decommissioning project of NPP A-1 in Slovakia it is necessary to decontaminate, monitor and if possible
to free release large amounts of contaminated materials, mainly contaminated soil and concrete debris (thousands of tons). Their
contamination is caused by dominant 137Cs (33 years after shutdown) that emits 661.65 keV gamma ray that can be easily detected
by scintillation or semiconductor detectors. In this connection a new free release monitoring post with a large volume 600 L container
counting geometry was designed and developed. The monitoring system is based on a pair of electrically cooled semiconductor
HPGe detectors that are placed into a modifiable vertical or horizontal pair of lead collimators. The detectors are equipped
with a Canberra Packard gammaspectrometry chain including proper characterised HPGe detectors type GC 3020. The vertical
arrangement of the collimator ensures monitoring of materials in 200 l rotating drums. The horizontal one ensures monitoring of
the one side of a 600 l rectangular container. The monitoring system is integrated with an industrial scale for determination of massic
activities of measured materials and in addition by a rotating table in the case of 200 l drums monitoring. Full-energy peak detection
efficiency polynomial curves…
A-4) LASER REMOVAL OF CONTAMINANTS ON THE METAL SURFACE (wP-59343)
Hui Jun Won, Jei Kwon Moon, Sun Hee Jung, Chong Hun Jung,
Kune Woo Lee, Korea Atomic Energy Research Institute;
Byung -Sun Choi, Korea Atomic Energy Research Institute (Korea)
A Q-switched Nd:YAG laser with a 532 nm and 450 mJ/pulse was employed to study the decontamination characteristics of
Type 304 stainless steel specimens and aluminum specimens artificially contaminated with CsNO3 , Co(NH4 ) 2 (SO4 )2, Eu2O3 and
CeO2 , respectively. The relative atomic molar ratio of the contaminants on metal surface before and after laser irradiation was determined
by EPMA. The morphology of specimen surface was examined by SEM. The optimum number of laser shots and the laser
fluence for the system were determined. More than 98 % of CsNO3 , Co(NH4 ) 2 (SO4 )2, Eu2O3 on Type 304 stainless steel specimens
could be removed by the circular type laser beam within the 16 laser shots at 13.3 J/cm2 and 10 Hz. The removal of contaminants
on aluminum surface, however, was found to be more difficult by laser. Comparative study on the removal characteristics
between the circular type laser beam and the string type laser beam was also performed. The variation of laser removal performance
on the contaminants was investigated by changing the irradiation angle.
A-5) INFLUENCE OF THE CONDITIONAL RELEASE OF THE MATERIALS WITH VERY
LOW LEVEL OF RADIOACTIVITY ON THE ENVIRONMENT (wP -59132)
Slavka Prvakova, University of Economics in Bratislava; Adela Mrskova, DECOM, A. S.;
Jozef Pritrsky, DECOM (Slovakia)
Significant amount of solid materials (metals, non-metals, building structures) that could be contaminated or activated is produced
during operation and especially decommissioning of nuclear power plants. Considerable fraction of these materials has level
of radioactivity close to the radiological limits allowing its safe release into the environment thereby could be potentially recycled
within the special constructions, as for example tunnels, roads or bridges. If the requirements of legislation on the radiological limits
for handling such material and long term safety of the constructions are fulfilled, contaminated material can be released in the
form of recycled concrete, remelted steel, etc.
The paper presents implementation of the IAEA and EC recommendations into the form of detailed analytical approaches with
the aim to develop integrated scenarios and to analyse long-term influence of the conditional release of the material with very low
level of radioactivity on the environment. Further, an estimation of the key input parameters characteristic for the specific conditions
of Slovak case in order to fulfil the radiological limits according to the Slovak legislation is included. Analysed integrated scenarios
represent surface or underground civil construction with radionuclides released directly into the geosphere and transported
by a groundwater flow into the biosphere. The migration of radionuclides is modelled in the near-surface conditions with the advection
as a dominant transport mechanism. Computer code GoldSim is used to evaluate the long-term safety assessment of the conditionally
released material on the environment.
A-6) CONDITIONAL RELEASE OF STEEL FROM DECOMMISSIONING
IN A FORM OF REINFORCED CONCRETE (wP -59058)
Jozef Pritrsky, DECOM; Miroslav Brodnan, University of Zilina;
Vladimir Necas, Slovak University of Technology (Slovakia)
The paper deals with the conditional release of low-level radioactive steel from decommissioning in a form of reinforced concrete.
The main goal was to determine limits for radionuclides concentration and calculate the annual dose for a member of a critical
group of public, which should not exceed 0.01 mSv/year (according to IAEA Safety Guide RS-G-1.7). Corrosion is the principle
mechanism of radionuclides release in this case, therefore effort was devoted to assess the time-dependent rate of steel reinforcement
corrosion. It was assumed, that concrete is initially highly alkaline (with pH of 12 to 13) because of hydration products
such as calcium hydroxide, which keeps the steel surface passive and protected from corrosion. However, carbonic acid resulting
from carbon dioxide and water in the atmosphere can react with these products to produce calcium carbonate. This process is
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Abstracts Session 39
referred to as a -carbonation and leads after a period of time to significant reduction of the alkalinity (to pH as low as 8.5) followed
by destruction of passive layer and starting corrosion of the embedded steel. The analytical principles and a set of input data have
been implemented into a mathematical model developed by means of GoldSim software. The paper presents the results of mathematical
simulation of corrosion precess, which are compared with real measured values.
A-7) DECOMMISSIONING OF THE UF6 SPHERE (w/oP -59200)
Sylvain Chevassu, ONET Technologies - ONECTRA (France)
Technically, ONECTRA has started with the decontamination, under containment, with a teleoperated arm. The complete operations
of internal cleaning and radiological controls will be operated with this arm. The internal particles are carried out applying
two distinct processes: first, a mechanical decontamination process (brushing/aspiration), followed by a chemical decontamination
process (pulverization of an acid solution). At the end of internal cleaning, the lower part of Sphere will be cut under containment
with mechanical-cutting tools. An internal radiological map will validate that the final decontamination objectives have been
reached. The final validation of the Spheres internal cleaning will be delivered through the agreement of the safety authority, mainly
based at the end of the operation report.
This safety authoritys agreement will allow the final Spheres dismantling sequence, consisting in outdoor cutting operations
with no containment using oxy-gas cutting processes. The last step consists in building a cover slab under the Sphere. This last step
requires a second agreement from the safety authority.
A-8) DEVELOPMENT OF NUCLEAR FACILITIES PIPING CLEANING
SYSTEM USING MICROBUBBLE (w/oP-59070)
Jongseon Jeon, SangChul Lee, Byoungsub Han, Enesys Co., LTD.;
HakSoo Kim, Nuclear Engineering & Technology Institute; Wisoo Kim, Enesys Co., Ltd. (Korea)
It removes radioactive sludge and corrosion products deposited on the inner walls of the pipes and valves in replacement or
decommission, upon termination of life time, of nuclear power plant or nuclear facility. It lowers a cost of waste treatments taking
advantage of a reduction of quantity of radioactive wastes by treating in classification of the radioactive wastes whose activities are
lower than legal standards.
The cleaning or decontamination methods developed until now have induced a damage on systems while being operated. A
decontamination has been restrained if it was difficult to access physically. We are in development of the cleaning technique for
pipelines by utilizing micro-bubbles in order to improve an efficiency and to prevent from any damage of systems. It aims to conduct
a decontamination for spaces difficult to access there by applying cavitation phenomenon that is generated in collapse of
micro-bubbles. In order to improve an efficiency of the micro-bubble device, the experimental conditions suitable to decontamination
have been established and the auxiliary equipments have been added. The generation conditions and characteristics of microbubbles
have been demonstrated by adjusting pHs and temperatures of cleaning solution. A decontamination effect has been confirmed
by adding up an electrolytic method and ozone into micro-bubbles.
A-9) A MATRIX INVERSION METHOD FOR GAMMA-SOURCE MAPPING
FROM GAMMA COUNT DATA (wP -59082)
Richard Bull, Claire Burgess, Ian Adsley, Nuvia Limited (UK)
Gamma ray counting is often used to survey the distribution of active waste material in various locations. Ideally the output
from such surveys would be a map of the activity of the waste. In this paper a simple matrix inversion method is presented. This
allows an array of gamma-count data to be converted to an array of source activities.
For each survey area the response matrix is computed. The elements in this matrix are calculated using a gamma shielding code
such as MicroShield (1). This matrix links the activity array to the count array. The activity array is then obtained via numerical
matrix inversion. The method was tested on artificially created arrays of count data onto which statistical noise had been added.
The method was able to reproduce, quite faithfully, the original activity distribution used to generate the dataset.
The method has been applied to a number of practical cases, including the distribution of activated objects in a hot cell and to
activated nimonic springs amongst fuel-element debris in vaults at a nuclear plant.
Reference
1) MicroShield, Version 8, Grove Software, 2009.
A-10) DECOMMISSIONING ACTIVITIES FOR SALASPILS RESEARCH REACTOR (wP -59055)
Andris Abramenkovs, Latvian Environment, Geology and Meteorology Centre;
Jazeps Malnacs, State Environmental Service (Latvia)
In May 1995, the Latvian government decided to shut down the Salaspils Research Reactor (SRR). The reactor is out of operation
since July 1998. A conceptual study for the decommissioning of SRR has been carried out by Noell-KRC-Energie- und
Umwelttechnik GmbH at 1998-1999. The Latvian government decided to start the direct dismantling to green field” in October 26,
1999. The upgrade of decommissioning and dismantling plan was performed in 2003-2004 years, which change the main goal of
decommissioning to the brown field.
The paper deals with the SRR decommissioning experience during 1999-2010. The main decommissioning stages are discussed
including spent fuel and radioactive wastes management. The legal aspects and procedures for decommissioning of SRR are
described in the paper. It was found, that the involvement of stakeholders at the early stages significantly promotes the decommissioning
of nuclear facility.
Radioactive waste managements main efforts were devoted to collecting and conditioning of historical radioactive wastes from
different storages outside and inside of reactor hall. All radioactive materials (more than 96 tons) were conditioned in concrete containers
for disposal in the radioactive wastes repository Radons at Baldone site. The dismantling of contaminated and activated
components of SRR systems is discussed in paper. The cementation of dismantled radioactive wastes in concrete containers is discussed.
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Session 39 Abstracts
A-11) TECHNICAL JUSTIFICATION & CHOICE FOR REMEDIATION METHODS (wP -59398)
Mark Morton, Janaka Jayamaha, WorleyParsons (USA)
When out of normal material or very high activity is encountered in a D&D project, special considerations are needed. As the
source term increases, the level of attention to planning, project cost and risk management must increase as well. WorleyParsons
Polestar (WPP) is engaged in defining and documenting (with follow on project design expected) the remediation methods to
remove contaminated soils discovered under a hot cell. Soil dose rates have been measured in the 7000 to 8900 Rem/hour, with
radionuclide mix to be defined in mid to late summer 2011 from samples drawn in June 2011. The scope of the current project is
to search remedial techniques and removal methods and define a set of possible alternatives. These alternatives will be screened
by WPP and client expert panel using a WPP defined process to short list the project alternatives. Transparency and un-biased
choice of actions is key to owner and public confidence in the process and the choice of the ultimate path forward.
The poster will show Phase 1- how possible means and methods were first identified, catalogued and the initial screening of
the means and methods (technologies). The remaining means and methods are being mixed to form an alternative…
A-12) NEW GENERATION OF DIAMOND TOOLINGS FOR FACILITATING
DECOMMISSIONING OPERATIONS (wP-59396)
Claude Besson, Erico Mariotti, Alexandre Mouysset, Lorenz Zur Nedden,
Bernard Delannay, Carbodiam (France/Belgium)
Diamond tools are well proven cutting, drilling and grinding technologies in many applications but need to be specifically optimized
and adapted for the complex and varied structures of nuclear power plant in view of decontamination and decommissioning.
The proper development and use of diamond tools in these extreme and complex conditions can only be achieved thanks to the
combined talent of experienced nuclear plant contractors, engineers, technicians, operators of diamond tools, and the use of specialized
equipment.
This present paper is an overview of the possible applications of diamond tools in the different operations of Nuclear Decommissioning
and Decontamination.
KEY DIAMOND TOOL APPLICATIONS for Decommissioning and Decontamination of Nuclear Power Plant:
1) Wet/dry concrete wall sawing (with remote control system)
2) Wet/dry wire cutting of concrete
3) Wet/dry wire sawing of metal
4) Wet/dry core drilling
5) Grinding and leveling for surface preparation including all edges
6) Scraping for removing bituminous or neoprene glues and all kinds of coatings
7) Shaving for horizontal and vertical surfaces and ceilings
Each situation requires a detailed feasibility study and engineering report to select the optimal work method and answer concerns
about safety, time to completion and waste volume...
A-13) POMPE SECONDAIRE (w/oP -59413)
Anne Durand, CEA (France)
La caractérisation globale du composant a permis de classer entièrement la pompe secondaire en déchet TFA.
Une étude a été menée avec lANDRA sur la faisabilité et les travaux de préparation à réaliser afin dévacuer en pièce unitaire
cette pompe vers le centre CSTFA.
Après son basculement en position horizontale, le corps de pompe (partie cylindrique) a été préparé* afin dassurer son remplissage
en mortier au CSTFA.
A-14) TRITIUM ANALYSIS : AN ACTUAL PROBLEM FOR LARGE
BUILDING DECOMMISSIONING (w/oP-59406)
Pascal Fichet, Florence Goutelard, Sylvie Guegan, Aurelie Robert-Ortis,
Nadine Evenat-Robic, Commissariat à l’Energie Atomique (France)
Radioactive waste management is nowadays, after nearly 50 years of concern, a technical and economical challenge faced by
existing nuclear power countries. In decommissioning of nuclear facilities and after disposal of the nuclear equipments (laboratory
materials, glove boxes, &), the radioactive inventory of the various building materials is needed to state the working condition
for dismantling.
A 150 m² laboratory which accommodated preparations of 3H and 14C labeled molecules is currently under investigation in
order to be dismantled in the next decade. 3H is particularly difficult to measure because of its lability and because of the low energy
of its beta emission. In order to classify the various building materials, different techniques of measurements have been implemented
after a grid has been marked on the floor. Firstly, a smear of each square was carried out and 3H was analyzed leading to
a first radiological area classification. Secondly, the technique called digital photo stimulated luminescence (PSL) autoradiography
(usually used in biology) has been developed in order to identify radioactive spots in the laboratory. This technique consists in
depositing the radiation sensitive film on the floor. After an exposure time of two days, a scan by laser leads to a 2D image…
A-15) REUSE OF CONDITIONALLY RELEASED STEELS; PROPOSAL AND EVALUATION
OF PROCESSES FOR MANUFACTURING OF STEEL ELEMENTS AND
FOR CONSTRUCTION OF SELECTED SCENARIOS (wP-59130)
Peter Bezák, Eva Hajková, Frantisek Ondra, Vladimír Daniska, DECOM, a.s.;
Vladimir Necas, Slovak University of Technology (Slovakia)
Conditional release of steels from decommissioning projects enables controlled reuse of considerable volumes of steels. For
proposal of scenarios for steel reuse, it is needed to identify and evaluate partial elementary activities of the whole process from
conditioned release of steels, manufacturing of various elements up to realisation of scenarios. As the scenarios for reuse of conditional
released steel are considered the technical constructions such as bridges, tunnels, roads, railway constructions and others
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Abstracts Session 39
which guarantee the long-term properties over the periods of 50-100 years. The paper presents the review of activities for manufacturing
of various steel construction elements made of conditionally released steels and activities for realisation of selected scenarios
for reuse of such construction elements. As the starting material for manufacturing of steel elements are the ingots as the
product of melting within the frame of decommissioning radioactive materials management. These ingots are re-melted in industrial
facilities in order to achieve the required physical and chemical properties. Most used technique for manufacturing the steel
construction elements is rolling. As the products considered in scenarios for reuse of conditionally released steels are bars for reinforcement
concrete, rolled steel sheets and other general rolled steel profiles. Lists of elementary activities are…
A-16) THE ASSESSMENT OF THE WASTE MANAGEMENT PLAN TO DECOMMISSIONING
OF CERNAVODA NPP FOR ENVIRONMENTAL IMPACT REDUCTION (wP-59358)
Gheorghe Barariu, National Authority for Nuclear Activity -
Subsidiary of Technology and Engineering for Nuclear Project (Romania)
At present, most of radioactive wastes generated in Romania are due to nuclear activities related to power generation at Cernavoda
NPP Unit 1, commissioned in 1996. By the commissioning in 2007 of Cernavoda NPP Unit 2, nuclear power production
doubled, and as a result the radioactive waste volumes doubled for this industrial activity field.
Nuclear and Radioactive Waste Agency - AN&DR strategy on low and intermediate level waste disposal, has as objective the
commissioning of Final Repository for Low and Intermediate Level Waste - DFDSMA until 2017. This facility is in the responsibility
of AN&DR. On the other hand wastes arising from Cernavoda NPP must be treated in order to achieve the acceptance criteria
of DFDSMA. Corresponding Radioactive Waste Treatment Facility - RWTF is in the responsibility of Cernavoda NPP.
Main objective of the National Policy for radioactive waste management is to assure a theoretic nul negative impact or a practical
minimum reasonable impact of the waste management activities on population and environment.
The volume of low and intermediate level wastes that result from decommissioning of four units CANDU 6 and the environment
impact reduction will be presented in this paper.
The treatment facility for radioactive wastes generated by decommissioning
A-17) APPLICATION OF THE DATA QUALITY OBJECTIVE PROCESS TO THE PARTIAL
DE-LICENSING AT OLDBURY NUCLEAR POWER STATION (WP -59376)
Denis Buckley, Magnox Ltd, Berkeley (UK)
Early in 2011 Oldbury Nuclear Power station in South West England applied to the Office of Nuclear Regulation (ONR) to delicense
an area of over 30 hectares of licensed land. This is the largest area of licensed land in the UK to undergo this procedure.
As part of the process the site prepared a safety case to support the submission to the ONR. Also there has been a requirement to
do sampling and analysis to characterise the land and show that any radioactive contamination is below the criterion for de-licensing.
This has been achieved through the successful application of the Data Quality Objective (DQO) process which enabled both
site and regulators to agree on the quantity of samples and the degree of analysis. The ONR has now issued the variation to Oldbury
in July 2011 de-licensing approximately 32 hectares of land from regulatory control.
This Paper outlines the process including the decisions and criteria that have been applied to the Sampling and Analysis at Oldbury
and the Treatment and Interpretation of the data.
This Paper outlines the process including the decisions and criteria that have been applied to the Sampling and Analysis at Oldbury
and the Treatment and Interpretation of the data.
A-18) MULTI-SITE RISK-BASED PROJECT PLANNING, OPTIMIZATION, SEQUENCING & BUDGETING
PROCESS AND TOOL FOR THE INTEGRATED FACILITY DISPOSITION PROJECT (wP -59394)
Jerel Nelson, Carlos Castillo, Julie Huntsman, Heather Lucek, WorleyParsons; Tim Marks, Omega Consultants (USA)
Faced with the DOE Complex Transformation, NNSA was tasked with developing an integrated plan for the decommissioning
of over 400 facilities and 300 environmental remediation units, as well as the many reconfiguration and modernization projects
at the Oak Ridge National Laboratory (ORNL) and Y-12 Complex. Manual scheduling of remediation activities is time-consuming,
labor intensive, and inherently introduces bias and unaccounted for aspects of the scheduler or organization in the process.
Clearly a tool was needed to develop an objective, unbiased baseline optimized project sequence and schedule with a sound technical
foundation for the Integrated Facility Disposition Project (IFDP).
In generating an integrated disposition schedule, each project (including facilities, environmental sites, and remedial action
units) was identified, characterized, then ranked relative to other projects. Risk matrices allowed for core project data to be extrapolated
into probable contamination levels, relative risks to the public, and other technical and risk parameters to be used in the
development of an overall ranking. These matrices ultimately generated a complete data set that were used in the Ranking and
Sequencing Model (RSM), commonly referred to as the SUPERmodel ,for its numerous abilities to support D&D planning, prioritization,
and sequencing. The SUPERmodel provides rough order-of-magnitude cost estimating,…
SESSION 39B — POSTER SESSION: ENVIRONMENTAL REMEDIATION POSTERS (4.1)
B-1) RADIUM REMEDIATION IN CANADA - HISTORY AND PRESENT DAY (w/oP-59157)
Mark Gardiner, Michael Owen, Robert Zelmer, AECL (Canada)
The environmental impact of radium remains even today. Radio-luminescent paints, radium therapy needles, mining and processing
and their associated legacies have long been pursued in France, Canada, the USA and other countries. The management of
these tasks provides a rich and fascinating history as well as successes and lessons learned in environmental remediation. In Canada,
the radium story begins with the discovery of pitchblende on the shores of Great Bear Lake in Canadas far north and its transport
south and refinement in Port Hope, Ontario. In the earliest days, the leading characters were the LaBine brothers, involved in
exploration and mining, and at the recovery and refining end, Carl French and Marcel Pochon, a protégé of Marie Curie, all associated
with the Eldorado Mining and Refining Company .
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To the current day in Canada, the work of environmental remediation of the radium legacy largely follows the trail of these
individuals, just as in France, a parallel effort follows the trail of Madame Curie. The Low-Level Radioactive Waste Management
Office is the agent of the Canadian government for its responsibilities regarding the work at the affected sites and the management
of the related wastes. The Office operates programs and facilities to…
B-2) MATHEMATICAL MODELING OF REACTIVE TRANSPORT IN GROUNDWATER WITH METALS
AND DISSOLVED ISOTOPES 226RA AND 228RA, USIN, SÃO PAULO, BRAZIL (w/oP-59245)
Rodrigo Raposo de Almeida, Federal Fluminense University; Valter Mortágua, Industrias Nucleares do Brasil;
Felipe Rosa, Luciano Magalhaes, Universidade Federal Fluminense (Brazil)
This paper aims to present the results of the analytical model of transport and the mathematical model of flow and transport of
radionuclides, considering the decay and adsorption of the byproducts. The study area is located in Sao Paulo, the largest city in
Brazil and Latin America with about 11 million inhabitants, and it is a former unit of processing of rare earths which ran between
the years 1960 and 1996 named the Plant Interlagos (USIN). The work focus is on groundwater contamination that occurred inside
Warehouse A. This contamination of soil and groundwater occurred about in 1991 due to a crack and leak from a box of separation
of ammonium chloride containing some dissolved radionuclides. The main source of contamination is no longer active, however
the residual phase in the vadose zone still there as a secondary source of contamination. Monitoring of groundwater is done periodically
since 1992, but only in 2007 a detailed groundwater study was undertaken from the impacted area. This study aimed to
detail the plume of contamination of metals and radionuclide in Warehouse A (Galpão A). With the software 3GEO Bioscreen SI
was developed an analytical model of transportation to establish and calibrate the parameters…
B-3) QUANTIFYING THE RETENTION OF FOAM FORMULATION COMPONENTS TO SEDIMENTARY
PHASES TO ENABLE PREDICTIONS OF MOBILITY AND TREATMENT EFFICACY (w/oP-59369)
Rosa Ramirez, DOE EM; Danielle Jansik, Dawn Wellman, Pacific Northwest National Laboratory (USA)
Deep vadose zone remediation remains the most challenging remediation problem in the DOE Complex. Foam delivery technology
is being developed as a method for delivering remedial amendments within vadose zone environments for in situ contaminant
stabilization. Thus far, the physical propagation of foam within subsurface media has been evaluated and quantified. However,
foam propagation is a product of surfactant sorption which directly impacts foam stability. In order to predict the stability of
foam during subsurface transport it is necessary to quantify the sorption of foam components as a function of concentration, competitive
sorption, sediment mineralogy, and temperature. This investigation provides the results of standard static batch test quantifying
these relationships. High Performance Liquid Chromatography (HPLC) was used to measure surfactant concentrations. The
results of this investigation provide necessary understanding to predict foam stability during subsurface transport and determination
of the remedial radius of influence. This study is part of a multiple step process for demonstrating the feasibility of foam transport
to distribute amendments within in the vadose zone.
B-4) TECHNIQUES OF RADIOACTIVE SOIL PROCESSING AT REHABILITATION
OF CONTAMINATION TERRITORIES. (wP-59199)
Victor Volkov, Alexander Chesnokov, Alexey Danilovich, Yury Zverkov, Sergey Koltyshev,
Sergey Semenov, Anatoly Shisha, RRC Kurchatov Institute (Russia)
Rehabilitation of nuclear- and radiation objects assumes dealing with and removal of considerable volumes of a radioactive
soil. A similar situation was faced at the remediation of such sufficiently large objects, as old radioactive waste storages at the territory
of «Kurchatov Institute» and elimination of consequences of radiation accident at Podolsk plant of nonferrous metals. At
rough estimates the volumes of a radioactive soil at territory of «Kurchatov institute» were 15-20 thousand cub.m, volumes of a
removed soil at carrying out of urgent measures in territory of Kirovo-Chepetsk chemical plant exceeded 20-25 thousand cub.m,
volumes of a low active waste at the territory of Podolsk plant may reach 20 thousand cub.m.
Such considerable volumes demand creation of technologies of their processing, an effective measuring technique of levels of
their contamination and ways of considerable (in times) decrease of their volumes at the expense of decontamination or separation.
Works have been aimed at the decision of these problems at carrying out of rehabilitation of territory «Kurchatov institute». During
works technologies of radiation and water-gravitational separation of a radioactive soil have been offered and are realized in
practice. A facility of water -gravitational separation of the soil was created and used within…
B-5) OPTIMISATION (SAMPLING STRATEGIES AND ANALYTICAL PROCEDURES)
FOR SITE SPECIFIC ENVIRONMENT MONITORING AT THE AREAS OF
URANIUM LEGACY SITES CONTAMINATION CONCERN IN UKRAINE (wP-59045)
Oleg Voitsekhovych, Tatiyana Lavrova, Alexander Kostezh, Ukrainian Hydrometeorological Institute (Ukraine)
There are many sites in the world, where Environment are still under influence of the contamination related to the Uranium
production carried out in past. Author’s experience shows that lack of site characterization data, incomplete or unreliable environment
monitoring studies can significantly limit quality of Safety Assessment procedures and Priority actions analyses needed for
Remediation Planning. During recent decades the analytical laboratories of the many enterprises, currently being responsible for
establishing the site specific environment monitoring program have been significantly improved their technical sampling and analytical
capacities. However, lack of experience in the optimal site specific sampling strategy planning and also not enough experience
in application of the required analytical techniques, such as modern alpha-beta radiometers, gamma and alpha spectrometry
and liquid-scintillation analytical methods application for determination of U-Th series radionuclides in the environment, doesnt
allow to these laboratories to develop and conduct efficiently the monitoring programs as a basis for further Safety Assessment in
decision making procedures. This paper gives some conclusions, which were gained from the experience establishing monitoring
programs in Ukraine and also propose some practical steps on optimization in sampling strategy planning and analytical procedures
to be applied for the area required Safety assessment and justification for its potential remediation and safe management.
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Abstracts Session 39
SESSION 39C — POSTER SESSION: MAJOR INSTITUTIONAL ISSUES IN
ENVIRONMENTAL MANAGEMENT / PUBLIC INVOLVEMENT (5.1)
C-1) VIRTUAL REALITY TECHNOLOGY FOR RADIATION VISUALISATION DURING
THE REMEDIATION AT ANDREEVA BAY IN RUSSIA AS SUPPORT TO
OPERATIONAL AND REGULATORY SUPERVISION (wP-59400)
Niels-Kristian Mark, Institute for Energy Technology,
Malgorzata Sneve, Norwegian Radiation Protection Authority (Norway)
The Norwegian Radiation Protection Authorities (NRPA) has since 1996 carried out a program of regulatory support projects,
funded by the Norwegian Ministry of Foreign Affairs (NMFA) The objective of the program has been to support the Russian civilian
and military regulators, the Federal Medical Biological Authorities of Russia (FMBA) and the Federal Environmental, Industrial
and Nuclear Supervision Service of Russia, as well as the corresponding nuclear and radiation safety authority within the Russian
Ministry of Defense with development and implementation of methods and tools for better regulatory supervision of the Andreeva
Bay and Gremikha Sites of Temporary Storage (STS) for Spent Nuclear Fuel (SNF) and Radioactive Waste (RW).
In 2005-2009 regulatory investigations were completed at the Andreeva Bay and Gremikha within the collaborative NRPA-
FMBA program. The radiation and radio-ecological situation was assessed, and criteria and regulations of the STS remediation
were developed, as well as the guidance for their application for three possible options of environmental remediation (conservation,
conversion and liquidation). As part of the project the Federal Medical-Biological Centre, a technical support organisation to
FMBA, developed the DOSEMAP and DATAMAP applications for the FMBA, supporting radiation risk monitoring, worker radiation
exposure control and deeper understanding of the evolution of…
C-2) TAKING RISK ASESSMENT AND MANAGEMENT TO THE NEXT LEVEL (wP-59395)
Jerel Nelson, Russel Lee Morton, WorleyParsons Polestar; Carlos Castillo, WorleyParsons;
James T. McSwain, Terragraphics; George Dyer, Natalie Johnson, WorleyParsons;
Gary Nick Kruskall, Link Technologies (USA)
A multi-level (facility and programmatic) risk assessment was conducted for the facilities in the Nevada National Security Site
(NNSS) Readiness in Technical Base and Facilities (RTBF) Program and results were included in a new Risk Management Plan
(RMP), which was incorporated into the fiscal year (FY) 2010 Integrated Plans. Risks, risk events, probability, consequence(s),
and mitigation strategies were identified and captured, for most scope areas (i.e., risk categories) during the facilitated risk workshops.
Risk mitigations (i.e., efforts in addition to existing controls) were identified during the facilitated risk workshops when the
risk event was identified. Risk mitigation strategies fell into two broad categories: threats or opportunities. Improvement projects
were identified and linked to specific risks they mitigate, making the connection of risk reduction through investments for the annual
Site Execution Plan.
Due to the amount of that was collected, analysis to be performed, and reports to be generated, a Risk Assessment/ Management
Tool (RAMtool) database was developed to analyze the risks in real-time, at multiple levels, which reinforced the site-level
risk management process and procedures. The RAMtool database was developed and designed to assist in the capturing and analysis
of the key elements of risk: probability, consequence, and impact. The…
C-3) RADIOACTIVE WASTE, FROM MYTH TO REALITY: THE STAKES FOR
ANDRA’S EDUCATIONAL COMMUNICATION EFFORTS (w/oP-59287)
Annabelle Comte, Andra (France)
Andra is responsible for proposing and implementing industrial management solutions for France’s radioactive waste. Andra’s
goal is to ensure that everyone has the opportunity to make up his or her own mind on a subject that generates such heated debate
within our society. This duty of communication is enshrined in law and is an integral part of Andra’s activities, in the same way as
research, industry and risk management.
Because the subject of radioactive waste is a complex one and concerns such a variety of audiences, Andra adapts its communication
policy so that it is accessible to all, according to individual needs and levels of interest.
For the “non-specialists” (general public, young people, etc.) Andra proposes a system built around education and awarenessraising.
Its aim is to make the subject of radioactive waste accessible to and comprehensible to as many as possible.
Its educational communication approach is built on 3 pillars: first and foremost information, the keystone of any system of
communication, then explanation and finally sharing with the legitimate stakeholders in this pedagogical approach.
Providing dependable information Andra offers information that is appropriate to the level of knowledge of its audiences and
uses all communication media, from the most…
SESSION 40— D&D MANAGEMENT APPROACHES AND PLANNING TOOLS (3.6)
1) IMPLEMENTATION OF THE STANDARDISED LISTING INTO DECOMMISSIONING
COSTING; EXAMPLES AND RELATED IAEA PROJECTS (wP-59313)
Vladimír Daniska, DECOM, a.s.; Michele Laraia, Paul Dinner, Patrick O’Sullivan, IAEA (Slovikia/Austria)
In 1999, IAEA, the OECD Nuclear Energy Agency and the European Commission jointly proposed a standardised listing of
activities to serve as a common basis for decommissioning cost estimates and thus promote greater harmonisation. This standardised
structure, which is based on activities at three hierarchical levels, is currently being updated based on the experience gained
over ten years of use. This paper comprises two main parts: in the first part, the revised standardised list of activities is presented,
together with guidance on its use in decommissioning costing. The three-level hierarchical structure has been retained though with
several detailed changes to ensure comprehensiveness and avoid ambiguity.
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Session 40 Abstracts
The second part the paper provides examples of cost methodologies based on the standardised list, including a cost estimation
model for research reactors and a spreadsheet-based cost estimation model, which might be used for scoping purposes or as a training
tool for cost estimators. The cost estimation model for research reactors at IAEA is intended for preliminary cost estimations
in IAEA member countries with limited previous experience in decommissioning costing. In this case, costs are determined largely
at the second level of the hierarchical structure of activities, as the more detailed cost information required for…
2) USE OF SOURCE TERM AND AIR DISPERSION MODELING IN PLANNING DEMOLITION
OF HIGHLY ALPHA-CONTAMINATED BUILDINGS (wP-59254)
James G Droppo, Bruce A. Napier, Jeremy P. Rishel, Pacific Northwest National Laboratory;
Richard W. Bloom, CH2M Hill Plateau Remediation Company (USA)
The current cleanup of structures related to cold-war production of nuclear materials includes the need to demolish a number
of highly alpha-contaminated structures. The process of planning for the demolition of such structures includes unique challenges
related to ensuring the protection of both workers and the public. Pre-demolition modeling analyses were conducted to evaluate
potential exposures resulting from the proposed demolition of a number of these structures. Estimated emission rates of transuranic
materials during demolition are used as input to an air-dispersion model. The climatological frequencies of occurrence of peak
air and surface exposures at locations of interest are estimated based on years of hourly meteorological records. The modeling
results indicate that downwind deposition is the main operational limitation for demolition of a highly alpha-contaminated building.
The pre-demolition modeling directed the need for better contamination characterization and/or different demolition methodsand
in the end, provided a basis for proceeding with the planned demolition activities. Post-demolition modeling was also conducted
for several contaminated structures, based on the actual demolition schedule and conditions. Comparisons of modeled and
monitoring results are shown. Recent monitoring data from the demolition of a UO3 plant shows increments in concentrations that
were previously identified in the pre-demolition modeling…
3) HOW AND INTEGRATED CHANGE PROGRAMME HAS ACCELERATED THE REDUCTION
IN HIGH RISK AND HIGH HAZARD NUCLEAR FACILITIES AT SELLAFIELD (wP-59014)
Angela Mackintosh, Sellafield Ltd. (UK)
For over five decades the Sellafield Site has been central to the UKs nuclear programme. Sellafield Ltd is managed by NMP
(Nuclear Management Partners), a consortium of URS, AMEC and AREVA and is focussed on the decommissioning of historical
facilities.
When the activity of Decommissioning commenced in the late 1980s the site focus at that time was on commercial reprocessing
and waste management. Now through the implementation of an integrated company change programme, emphasis has shifted
towards accelerated risk and hazard reduction of degraded legacy plants with nuclear inventory whilst ensuring value for money
for the customer, the Nuclear Decommissioning Authority (NDA).
This paper will describe the management approach that is being taken and the planning tools that are being applied by the Site
owners in delivering an integrated change programme across the Decommissioning Directorate.
The paper will explain how the management approach to change uses Peer Assist, Rapid Improvement Events, Organisational
Review Self Evaluation, Value Stream Analysis and Accelerated Improvement Events as improvement tools. Use of these has
enabled downsizing of the organisation, driven out hundreds of man day efficiencies within the maintenance and asset management
areas, improved the management of spares reducing annual costs by £1000s, improved Commercial…
4) USE OF IN-SITU GAMMA SPECTROSCOPY DURING NUCLEAR
POWER PLANT DECOMMISSIONING (w/oP-59340)
Richard McGrath, Karen Kim, Electric Power Research Institute (USA) - Presentation by Sean Bushart, EPRI (USA)
The Electric Power Research Institute (EPRI) is a non-profit research organization that supports the energy industry. The
Nuclear Power Plant Decommissioning Technology Program conducts research and develops technology for the safe and efficient
decommissioning of nuclear power plants.
One of the key objectives of the EPRI Decommissioning Technology Program is to capture the good practices and lessons
learned from plants currently undergoing decommissioning. Several major plant decommissioning programs have been successfully
completed, so EPRI is documenting relevant experiences to aid future decommissioning activities, both in the United States and
internationally. In-situ Gamma Spectroscopy is powerful technology with the potential for widespread application in nuclear power
plant radiological surveys.
Due to leakage and other events that may occur during nuclear power plant operations, soil, concrete and bedrock have the
potential to become contaminated, and therefore must be characterized to demonstrate that they meet strict regulatory site release
limits. The radiological surveys conducted during power plant decommissioning have historically been very labor intensive, time
consuming and often extend decommissioning duration. The use of hand-held survey meters was typical during early decommissionings.
As engineers gained experience, they often replaced the hand-held meters with advanced technologies such as the In-situ
Gamma Spectroscopy instruments. The…
5) LEGACY RADIOACTIVE WASTE STORAGE - MAGNOX SWARF STORAGE
SILO LIQUOR EFFLUENT MANAGEMENT (wP-59271)
Stephen Le Clere, Sellafield Ltd (UK)
The liquid effluent activity arising from Sellafield Ltds Magnox Swarf Storage Silo (MSSS) emptying operations represents
the greatest liquid effluent treatment challenge within the companys Legacy Ponds and Silos portfolio.
The Magnox Swarf Storage Silo (MSSS) was constructed to provide an underwater storage facility for irradiated magnox
cladding swarf that was removed from fuel prior to processing.
Construction of the original silo was initiated in the early 1960s, as the existing Pile Fuel Cladding Silo reached its storage
capacity however the original silo was filled by 1972 so three further silo extensions were constructed between the early 1970s and
mid-1980s.
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Abstracts Session 40
A significant programme of work has been underway over the last two decades, to support the programmes strategic intent of
retrieving and treat all legacy wastes and remediate the structures of both the legacy plant and the new build construction plants
necessary to support decommissioning.
The paper will look at the challenges faced by the team as they ready the facility for retrievals and decommissioning and discuss
how these were managed or overcome through a coordinated programme of work.
This will include a review of the significant asset restoration programme which culminated recently in the commencement of
production liquor transfers…
6) EXPERIENCE OF APPLICATION OF NEW REMOTE CONTROLLED INSTRUMENTS FOR SCANNING OF
DISTRIBUTION OF RADIOACTIVE CONTAMINATION IN ROOMS WITH HIGH DOSE RATE (wP-59354)
Vyacheslav Stepanov, Alexey Danilovich, Oleg Ivanov, Victor Potapov, Sergey Smirnov,
Anatoly Volkovich, NRC Kurchatov Institute (Russia)
When carrying out the decommissioning of nuclear facilities is necessary to measure the distribution of radioactive contamination
in the rooms and the equipment at high levels of background radiation. In the decommissioning of the reactor in the MR
Research Center “Kurchatov Institute” for such problems is developed and applied a few special systems with remote control. For
a survey of high-level objects used mounted on the robot radiometric system [V.E. Stepanov, etc. Using collimated radiometer systems
mounted on the robot for inspection of storage Brokk CPS inside the reactor MR Research Center “Kurchatov Institute”//
Atomic Energy. 2010. v.109. no4. P. 194]. To determine the composition of pollutants and use a portable collimated spectrometric
system [V.E. Stepanov et. Al. Remotely controlled collimated detector to measure the distribution of radioactive contamination //
Atomic Energy. 2010. v.109. no2. S. 106]. To obtain a detailed distribution of contamination of used remote-controlled gamma camera
[Stepanov V. E., et al. Application of portable gamma camera for the control on extraction of the radioactive wastes from temporal
storage in territory of RRC Kurchatov Institute// ICEM05/DECOM05 Glasgow 2005, Abstract Book pp.97]. Described works
conducted under the Federal Program for Nuclear and Radiation Safety of Russia.
7) HUMAN AND ORGANISATIONAL FACTORS AS KEY LEVERS OF PERFORMANCE
IN D&D PROJECT MANAGEMENT (W/OP-59323)
Thierry Flament, Bertrand Willmann, Grégoire de Laval, Jean-Louis Lemarch, Alain Cordoba, AREVA (France)
In a number pf D&D projects, the type of installations to be dismantled and the variety of their equipments (glove-boxes,
tanks&) and the products present on site (plutonium, uranium) in the form of powder are making many operations manual ones.
Key phases in HR and organisation management:
• The first D&D experience, the learning curve ramp-up
• To begin any project, you usually try to benefit from benchmark of similar projects to be able to build up the first scenario,
by using the best practices. The first experimental team consisted of operators who already had experienced dismantling
at least once in the course of their career.This first dismantling operation is preferably to be conducted on an installation
relatively poorly contaminated. This was to implement the correct techniques thus reducing the consequences of a possible
unforeseen event.
The capitalisation on the return on experience
The success of this first dismantling site operation allowed us to implement a process of experience feedback to build the scenarios
and the operating procedures of the following sites. In particular, targeted safety-security stop points are positioned for validation
on the operations by people responsible for safety and security.
• HR training
• Implementation of new equipments (saws, stalls&) allows experimental…
8) DEVELOPMENT OF COMPUTER PROGRAM FOR ESTIMATING DECOMMISSIONING COST (wP-59037)
HakSoo Kim, JongKil Park, Nuclear Engineering & Technology Institute (Korea)
The programs for estimating the decommissioning cost have been developed for many different purposes and applications. The
estimation of decommissioning cost is required a large amount of data such as unit cost factors, plant area and its inventory, waste
treatment, etc. These make it difficult to use manual calculation or typical spreadsheet software such as Microsoft Excel. The cost
estimation for eventual decommissioning of nuclear power plants is a prerequisite for safe, timely and cost-effective decommissioning.
To estimate the decommissioning cost more accurately and systematically, KHNP, Korea Hydro and Nuclear Power Co.
Ltd, developed a decommissioning cost estimating computer program called “DeCAT-Pro”, which is Decommissioning Cost
Assessment Tool Professional. (Hereinafter called “DeCAT”) This program allows users to easily assess the decommissioning cost
with various decommissioning options. Also, this program provides detailed reporting for decommissioning funding requirements
as well as providing detail project schedules, cash-flow, staffing plan and levels, and waste volumes by waste classifications and
types. KHNP is planning to implement functions for estimating the plant inventory using 3-D technology and for classifying the
conditions of radwaste disposal and transportation automatically.
SESSION 41 — D&D TECHNOLOGIES - PART 2 OF 2 (3.13)
1) AN INNOVATIVE PROCESS FOR SEGMENTING OF GUIDE TUBES (wP-59029)
Patrick (PJ) Gobert, Pierre-Henri Ponchon, Stefan Fallström,
Joseph Boucau, Westinghouse Electric Company (Belgium/France/Sweden)
The purpose of this paper is to describe an innovative process for segmenting PWR Guide Tubes (GT’s) and the service (training
and execution) that can be performed successfully and safely.
Over time, some utilities are replacing control rod GTs and store them in temporary disposal facilities. Due to lack of space, it
is sometimes needed to cut and condition them in waste packages for final disposal and waste treatment.
Based on its more than 20 years of strong experience and lessons learned in the development of nuclear components segmentation
and packaging technology, Westinghouse has recently developed a complete solution for cutting and consolidating GTs.
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Session 41 Abstracts
One of the challenges related to such equipment is to consider two routes for the waste management: one for the highly activated
segments and another for the less activated segments.
The length of the segments has been defined to minimize the volume of highly activated waste and therefore develop a process
which is adapted to the size of containers specified by the customer. A model with five cutting operations and generating six segments
has been chosen.
In order to minimize risks and ensure safety for people and facilities, radiological studies were performed for various configurations.
All…
2) ASSAY OF PLUTONIUM CONTAMINATED WASTE BY GAMMA SPECTROMETRY (wP-59039)
Ian Adsley, Michael Green, Ian Pearman, Mike Davies, Nuvia Limited (UK)
The extreme toxicity of plutonium necessitates the segregation of plutonium contaminated materials (PCM) with extremely
small (sub-?g) levels of contamination. The driver to accurately measure these small quantities of plutonium within (relatively)
large volumes of waste is (in part) financial. The range of waste costs in the UK varies considerably typically by an order of magnitude
for each step in category from Exempt, through VLLW, LLW and ILW.
Within the UK, there has been a historical reluctance to use low energy gamma radiation to sentence PCM because of the potential
for self attenuation by dense materials. This is unfortunate because the low-energy gamma radiation from PCM offers the only
practicable technique for segregating PCM within the various LLW and sub-LLW categories. Whilst passive neutron counting techniques
have proved successful for assay of waste well into the ILW category, a cursory study of the neutron yield data from spontaneous
fission and ?-n reactions reveals that these techniques are barely capable of detecting mg quantities of plutonium let alone
the sub-?g quantities present in LLW.
This paper considers the use of two types of gamma detector for assay of PCM: the thin sodium iodide FIDLER (Field Instrument
for the Detection…
3) REUSE OF CONDITIONAL RELEASED MATERIALS FROM DECOMMISSIONING; A REVIEW OF
APPROACHES AND SCENARIOS WITH LONG-TERM CONSTRUCTIONS (w/oP-59149)
Vladimír Daniska, Jozef Pritrsky, Frantisek Ondra, Ivan Rehák, Matej Zachar, DECOM, a.s,;
Vladimir Necas, Slovak University of Technology (Slovakia)
Paper presents the overall scope and actual results of the project for evaluation of representative scenarios for reuse of conditionally
released materials from decommissioning. Aim of the project is to evaluate the possibilities of reuse of conditionally
released steels and concrete in technical constructions which guarantee the long-term preservation of design properties over periods
of 50-100 years. Interaction of conditionally released materials with public is limited and predictable due to design and purpose
of selected constructions and due to fact that in many scenarios these materials are embedded in non-radioactive materials
such as bars in reinforced concrete. Workers scenarios for preparation, operation and maintenance of these constructions are
analysed in detail including the manufacturing of elements for these constructions. Project aims to evaluate the scenarios of reuse
of conditionally released materials in a complex way in order to develop the data for designers of scenarios and to evaluate the volumes
of conditionally released materials based on facility (to be decommissioned) inventory data. The long-term constructions considered
are bridges, tunnels, roads, railway constructions, industrial buildings, power industry equipment and others. Evaluation
covers following areas:
• Analysis of activities for manufacturing of reinforcement bars, rolled steel sheets and other steel elements and…
4) REMEDIATION OF A VENTILATION DUCT CONTAMINATED BY PA-231 (wP-59248)
Pete Burgess, Nuvia Ltd; Clare Irving, Forest Environmental; Keith Stevens, Nuvia Ltd, (UK)
Cambridge University had worked in the 1960s and 1970s with Pa-231, a decay product of U-235. The fume cupboards discharged
into ventilation ducting made from asbestos cement. The university wished to refurbish the laboratory and the RPA had
negotiated over many years with the Environment Agency to set up a project to remove the ducting both to reduce the radiological
hazards and as part of a programme to ,remove unwanted circuits and upgrade the ventilation system to modern standards. Contamination
levels were significant and low dose rates were measurable on the external surface. The aim was to be able to remove
the ducting and treat it as asbestos waste, rather than to have to treat the debris as asbestos contaminated radioactive waste. The age
of the contaminant was such that a large fraction of the decay chain had grown in, giving a mixture of alpha, beta and gamma emissions.
The most useful nuclides for surface monitoring were Pb-211 and Tl-207, both of which are energetic beta emitters. A wide
energy range beta detector was used, but it was fitted with a filter to absorb any alpha radiation which otherwise would have contributed
to the signal for good surfaces but not…
5) MEASUREMENT OF PLUTONIUM CONTAMINATION THROUGH PAINT USING A FIDLER PROBE (wP-59250)
Robert Clark, Pete Burgess, Nuvia Ltd; Ian Croudace, GAU-Radioanalytical Laboratories (UK)
Alpha contamination detection usually relies on good surface conditions - smooth, clean and flat. However, in many circumstances,
this is not the case, or it may be that there is a significant chance that contamination has been deliberately or accidentally
painted over. The alpha emitting isotopes of plutonium also emit significant L x-rays in the 11 to 20 keV energy range, as does Am-
241, which also emits a 60 keV gamma with a 36 % probability. These X-rays are unattenuated to any extent in air over a range
of 1 metre. They also penetrate paint significantly. The Fidler probe was designed as an efficient detector of these X and gamma
radiations. The window is thin beryllium and the scintillator is thin sodium iodide. This leads to a very efficient detection of both
the X-rays in question and the 60 keV gamma radiation while keeping the background as low as possible. The signal from such a
detector can be processed in several ways gross counting above a threshold, counting in regions of interest or full spectrometry.
The advantages of the latter include the minimisation of background, easy background correction, the ability to look at the recorded
X-ray spectrum and the…
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Abstracts Session 41
6) THE USE OF STANDARD ALPHA AND BETA SURFACE SCINTILLATION CONTAMINATION MONITORS TO
CONFIRM THE CONTAMINATION FINGERPRINT AND TO CHECK ON SOURCE QUALITY (wP-59249)
Pete Burgess, Nuvia Ltd (UK)
Normally, alpha and beta surface contamination monitors are used with a simple counting threshold, i.e. any pulse over a predetermined
amplitude is counted. This is very different from gamma monitoring, where the use of counting windows is very popular
and the use of full multi-channel analysis is common. Many current surface contamination ratemeters have the capacity to
drive dual phosphor detectors and can be set up to provide alpha and beta channels. Effectively, the beta channel is a counting window,
i.e. all pulses which are bigger than the threshold and smaller than the alpha threshold are counted. Larger pulses go into the
alpha channel.
This paper addresses how this can be used with beta only and alpha only detectors to provide information on the source. The
detector is set up conventionally to a plateau for the lowest beta energy anticipated. The instrument is then switched to alpha+beta
mode and the alpha threshold set to 3 times the beta threshold. With this set up, the alpha to beta channel count rate ratio varies
smoothly by a factor of 14 between Y-90 (Emax 2.27 MeV) and C-14 (Emax 0.16 MeV). Hence the instrument can be used to estimate
the energy of an…
7) CLEARANCE OF BUILDINGS OF NPP WÜRGASSEN (GERMANY) USING
AN INNOVATIVE CLEARANCE CONCEPT (wP-59280)
Stefan Woerlen, Marco Steinbusch, Alexander Kummer,
Stefan Thierfeldt, Frank Schartmann, Brenk Systemplanung (Germany)
The nuclear power plant Würgassen in Germany entered into decommissioning in 1995. The project has currently advanced to
the clearance of the buildings. Clearance of buildings has commenced in 2007 with establishing the clearance procedure in pilot
rooms. It has entered the productive phase in 2010 and will last until about 2014.
In 2007, Brenk Systemplanung has been commissioned by E.ON / NPP Würgassen to perform clearance of the pilot rooms in
the turbine building as well as of rooms with higher contamination levels in other buildings in 2010 and 2011. It has been one of
the goals of this work to establish an innovative clearance procedure which would not rely on 100% surface measurements but
which should be based on the use of in situ gamma spectrometry and the application of approaches to minimise the number of clearance
measurements.
Central points of the concept for clearance of buildings which is presented in this paper were the establishment of averaging
areas of up to 10 m², which is an ideal size for the use of in situ gamma spectrometry, and the application of statistical methods,
which allow an efficient performance of the clearance measurements. As a first step the measurement…
8) CHARACTERIZATION OF IRAQ’S REMOTE NUCLEAR FACILITIES
FOR DECOMMISSIONING AND WASTE MANAGEMENT (wP-59167)
Fouad Al-Musawi, Adnan S. Jarjies, Ministry of Science and Technlogy;
Ross Miller, Sandia National Laboratories (Iraq/USA)
The Government of Iraq (GOI) has engaged serious efforts to decommission and dismantle former nuclear facilities. The GOI
has only preliminary information on some of the former nuclear facilities, and this paper summarizes the missions that were undertaken
to characterize those facilities. The facilities are located at various sites throughout Iraq, from locations close to Baghdad to
those in the north and far western desert areas. Some of the facilities, such as those at the Al Tuwaitha Nuclear Research Center
have been visited and somewhat characterized. Other facilities, including the following, have not been visited or thoroughly characterized.
• Akashat Mine, Uranium ore production
• Al Qaim, Uranium enrichment facility
• Al Jesira, Uranium feed stock production facility
• Adaya, Burial location for contaminated equipment
• Al Tarmiya,Electromagnetic isotope separation site
• Rashdiya, Centrifuge development center
• Djerf al Naddah, Spent fuel storage facility
Missions were conducted to develop an inventory the buildings/structures that need to be included in decommissioning/dismantlement
efforts. The number of buildings, type of construction, size and general condition of the buildings was noted. In addition,
attempts were made to determine contamination levels and types on surfaces, equipment, rubble, etc. This information will
be used to support…
SESSION 42 — LIQUID WASTE TREATMENT PROCESS AND EXPERIENCE (1.8)
1) NUCLIDE SEPARATION BY HYDROTHERMAL TREATMENT AND ION EXCHANGE (wP-59217)
Georg Braehler, Ronald Rieck, NUKEM Technologies GmbH; Valentin Avramenko, Valentin Sergienko,
Sergej Shmatko, Valentin Dobrzhanskyi, Institute of Chemistry FEBRAS; Elmar Antonov, NTP (Germany/Russia)
Liquid low level radioactive effluents, when solidified in e g. cement matrix, contribute to a significant extend to the waste
amount to be disposed of in final repositories.
Accordingly, since many years scientists and engineers investigate processes to remove the radioactive nuclides selectively
from the effluents, to split the raw solution into two separate fractions: a large fraction with activity concentrations below the limits
for free release; and a small fraction, containing the activity in concentrated form one g ion exchanger materials (ion exchange
has proven to be the most promising method for such nuclide separation).
The challenge to be taken up is: When (and this is most often the case) the effluent contains organic materials and complexing
agents, the formation of e. g. the 60-Co-EDTA complex prohibits its fixation to the ion exchangers.
Accordingly the complexing agent needs to be removed or destroyed.
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Session 42 Abstracts
The Institute for Chemistry of the Russian Academy of Sciences has applied the method of hydrothermal treatment (at elevated
temperature and pressure, 200 °C, 200 bar), supported by Hydrogen peroxide oxidation, to allow virtually complete removal of
radioactive nuclides on inorganic ion exchangers.
Pilot plants have been operated successfully in Russian power stations, and an…
2) DECONTAMINATION OF STRONTIUM FROM LIQUID RADIOACTIVE
WASTES BY SODIUM NONATITANATE (wP-59083)
Merceille Aurélie, CEA Marcoule; Agnès Grandjean, Institut de Chimie Séparative de Marcoule;
Yves Barre, CEA Marcoule (France)
Environmental impact of toxic, biological and radioactive pollutants release is of great importance for all industrial societies
today. The development of efficient process for purification filtration and waste removal- of these industrials effluents is booming.[1]
Nuclear industry produces a wide range of radioactive liquid effluents. Many of these wastes need treatment in order to
reduce the quantities of radioactive contaminants and of course to reduce human exposure. 90Sr is one of the major pollutants in
nuclear liquid wastes. A promising way for extraction of this radioelement from mobile phase (liquid) to a solid phase is the use of
specific ion exchange solids. Contrary to conventional organic ion exchange resins, inorganic ion exchangers possess a number of
advantages such as superior chemical, thermal and radiation stability.
For strontium removal from aqueous solutions, many inorganic ion exchange solids are described in the literature. One of them
is sodium nonatitanate [3] which seems to be a very good candidate for this use. We present here a study of the effect of synthesis
temperature on the kinetics and on the adsorption capacity of this ion exchanger [2]. For this purpose, first, three materials were
synthesized at 100°C, 160°C and 200°C. They were compared thanks…
3) RUSSIA: RESULTS AND PROSPECTS OF LIQUID SOLIDIFICATION
EXPERIMENTS AT ROSATOM SITES (w/oP-59112)
Dennis Kelley, Pacific Nuclear Solutions (USA)
Ongoing experimental work has been underway at selected nuclear sites in the Russian State Atomic Energy Corporation
(ROSATOM) during the past two years to determine the effectiveness, reliability, application and acceptability of high technology
polymers for liquid radioactive waste solidification. The long term project is funded by the U.S. Department of Energys Initiatives
for Proliferation Prevention (IPP) program. IPP was established in 1994 as a non-proliferation program of DOE / National Nuclear
Security Administration and receives its funding each year through Congressional appropriation. The primary objective of IPP is
to engage former Soviet nuclear weapons scientists, currently or formerly involved with weapons of mass destruction, in peaceful
and sustainable commercial activities.
Argonne National Laboratory provides management oversight for this project. More than 60 former weapons scientists are
engaged in this project.
With the project entering its mid-point, the emphasis is now on expanding the experimental work to include the sub-sites of
Seversk (SCC), Zheleznogorsk (MCC) located in Siberia and Gatchyna (KRI) and applying the polymer technology to actual problematic
waste streams. Work to date includes the solidification of over 100 waste streams for the purpose of evaluating all aspects
of the polymers effectiveness with LLW and ILW complex waste. Waste…
4) PRE-TREATMENT OF ORGANIC LIQUID WASTE STREAM AT CERNAVODA NPP (w/oP-59079)
Gabriela Teodorov, Laszlo Toro, Adina Sandru, MATEFIN; Dennis Kelley, Pacific Nuclear Solutions;
Dorin Dumitrescu, NPP Cernavoda (Romania/ USA)
The radioactive waste management system at Cernavoda Nuclear Power Plant (NPP) was designed to maintain acceptable levels
of safety for workers and to protect human health and the environment from exposure to unacceptable levels of radiation.
During the ten years operation of the Cernavoda NPP, a series of waste streams have been developed for waste management
purpose. Some of these streams consist of radioactive organic liquid wastes: spent oils, spent solvents, liquid scintillation cocktails
(LSC), flammable solids (solid-organic liquid mixture) and sludge.
Effective treatment of organic liquids waste from the initial to the final stage has been a challenge for NPP Cernavoda. All components
of the organic liquid waste stream have been stored in liquid form in stainless steel drums in the Solid Radioactive Waste
Intermediate Storage Facility (SRWISF). This facility was originally designed for solid wastes only, consequently, the regulatory
body has asked Cernavoda NPP to remove the flammable liquids from this repository as soon as possible.
As a result, at the end of 2008, Cernavoda NPP initiated the solidification of organic liquid wastes (both historical and fresh
wastes) together with a separation of solids associated with the organic liquids. In accordance with terminology of the International
Atomic Energy…
5) TRANSPORT AND DEPOSITION PROPERTIES OF MODEL SLURRIES
OF ONE AND TWO PARTICLE SPECIES (wP-59140)
Hugh Rice, Simon Biggs, Michael Fairweather, James Young, University of Leeds, Leeds, (UK)
The UK nuclear industry has in its inventory legacy waste in the form of complex, polydisperse and polydense suspensions,
slurries and sludges in a variety of storage and transport vessels. This waste has been difficult to characterise because of radioactivity
and limited accessibility, and containment and disposal of the waste presents a continuing challenge. Our objectives are to
investigate the effect of mono- and bidisperse suspensions with a range of particle sizes and densities on the turbulence characteristics
and transport and settling behaviour of slurries that are chosen to be analogues of those found on nuclear sites. Two versatile
slurry pipe-flow loops of different diameters have been commissioned which can be operated over a large range of Reynolds numbers
and are amenable to ultrasonic, optical and physical measurement methods. In addition, a variety of particle characterisation
studies have been performed on the particle species that form the suspensions. In particular, the effect of settled beds on the flow
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Abstracts Session 43
velocity and turbulence characteristics and of inter-species interactions in bidisperse suspensions has been investigated. Results of
particle characterisation are presented, along with mean and turbulent velocity profiles over a range of Reynolds number and particle
concentration. The implications of the work for waste processing within the industrial context will be discussed in the full
paper.
6) APPLICATION OF A NEW TECHNOLOGY FOR REPROCESSING OF WASTES WITHIN THE FRAMEWORK
OF REHABILITATION OF URANIUM MINES OPERATED BY IN SITU LEACHING (wP-59403)
Gagik Martoyan, Garik Nalbandyan, Lavrenti Gagiyan,
AREV SI CJS Company; Gagik Karamyan, Artak Barseghyan, Gagik Brutyan, Ecoatom LLC (Armenia)
It is essential the environmentally safe industrial production of nuclear fuel especially in the case of uranium extraction by In
Situ Leaching, when the environment and the deep extraction of uranium are important problems. In the presented paper it is studied
the feasibility of the application of an electrodialysis method for the deep extraction of uranium and radium from liquid (acid)
streams. It is proposed to apply a new electrodialysis method to ensure the necessary extraction level of elements. In the same time
the new method ensures the recycling of acids used in the process.
7) A FULLY OPERATIONAL PILOT PLANT FOR ELIMINATING RADIOACTIVE
OILS MIXED WITH CHLORINATED SOLVENTS (wP-59044)
Albert Jacobs, William Everett, Dewdrops Company (France)
Disposal of organic liquid waste has become an increasing issue for many nuclear sites. Existing disposal solutions such as
incineration or super critical water techniques are not compatible with wastes containing chlorinated solvents or fluorine owing to
corrosion problems. As an example several hundred cubic meters of lubricating oils mixed with trichloroethylene (TCE) or perchloroethylene
(PCE) are stockpiled on several French nuclear sites. For several years Dewdrops has been developing an original
combination of mineralization processes for waste oils and solvents particularly well suited to the nuclear field. The patented technology
relies on the alternation of chemical and biological oxidation mechanisms. The oxidized organic material predominately
forms carbon dioxide, water and inorganic salts. This paper details the procedure and the results obtained for a particular case at
the Tricastin nuclear site of Areva NC (South France). The organic waste used in this study was a 85/15 v/v ratio mix of lubricating
oil and TCE. The pilot plant build upon the technology has a daily treatment capacity of approximately 10 liters. In the first
step the TCE is mineralized by the photo Fenton reaction. Using hydrogen peroxide with an ultraviolet regenerated iron catalyst,
TCE is transformed to carbon dioxide, water and…
8) ADSORPTION OF CESIUM RADIONUCLIDES BY THE COMPOSITE SORBENTS
CARBON FIBER/TRANSITION METALS FERROCYANIDES (wP-59255)
Irina Sheveleva, Veniamin Zheleznov, Svetlana Bratskaya, Valeriy Kuryavyi,
Valentin Avramenko, Institute of Chemistry FEBRAS (Russia)
Among various methods of cesium removal from aqueous solutions, sorption using transition metals (Ni, Zn, Cu, Fe) ferrocyanides
is the most efficient method due to extremely high affinity of cesium ions to ferrocyanides. Preparation of selective sorbents
by fixation of ferrocyanides crystals in porous matrix of natural clinoptilolite, synthetic zeolites, alumosilicates, and carbon
materials is an efficient way to increase decontamination factors and reduce sorbents expenditure in treatment of 137Cs-containing
wastewaters.
It is known that the efficiency of transition metals ferrocyanides application depends on the crystal size being the highest for
nanocrystals. Although nanocrystals are difficult to handle in a direct application, they can be used in composite materials. In this
case two main problems arise: how to control the crystal size of transition metals ferrocyanides and how to fix them reliably in the
supporting matrix.
In this paper we suggest a new route to preparation of composite materials selective to cesium ions using transition metals ferrocyanides
stabilized by siloxane-acrylate latexes. The size of transition metals ferrocyanides is controlled by the size of the latex
particles and their stability is determined by ionization of polyacrylic acid carboxylic groups on the functionalized latex surface.
These functionalized particles can be used as…
SESSION 43 — SITING, DESIGN, CONSTRUCTION, AND OPERATION
OF L/ILW DISPOSAL FACILITIES - PART 2 OF 2 (1.19)
1) 20 YEARS OF OPERATION FOR CENTRE DE L’AUBE
DISPOSAL FACILITY: LESSONS LEARNED (w/oP-59235)
Patrice Torres, Laurent Schacherer, Franck Duret, Pascal Lecoq, Alain Delaplanche, Michel Dutzer, Andra (France)
The presentation will show the evolution of the facility during thes 20 years: in terms of deliveries, of type of waste packages,
in terms of lexibility to answer the needs of waste generators, in terms of disposal vault design. Lessons leanrd will be emphasized.
It will provide information on the environmental monitoring of the facility.
2) DEMONSTRATION TEST OF UNDERGROUND CAVERN-TYPE
DISPOSAL FACILITIES FISCAL 2010 STATUS (w/oP-59180)
Yoshihiro Akiyama, Kenji Terada, Nobuaki Oda, Tsutomu Yada,
Takahiro Nakajima, Radioactive Waste Management Funding And Research Center (Japan)
The underground cavern-type disposal facilities for low-level waste (LLW) with relatively high radioactivity levels mainly generated
from power reactor decommissioning and for part of transuranic (TRU) waste mainly from spent fuel reprocessing are
designed to be constructed in a cavern around 100 meters below ground, and to employ an engineered barrier system (EBS) of a
combination of bentonite and cement materials in Japan. In order to advance the feasibility study for this disposal, The Demonstration
Test for Underground Cavern-Type Disposal Facilities has commissioned by Japanese government since fiscal 2005, and since
fiscal 2007 a full-scale mock-up test facilities has been constructed under actual subsurface environment. The main objective of the
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Session 44 Abstracts
test is to establish construction methodology and procedures which ensure the required quality of the engineered barrier system
(EBS) on-site. By fiscal 2010 some parts of the facilities has been constructed, and the test has demonstrated both practicability of
the construction and achievement of the quality. They are respectively taken as low-permeability of less than 5E-13 m/s and lowdiffusion
of less than 1E-12 m2 /s at the time of completion of construction. This paper covers the test results obtained by the construction
of some parts of a bentonite and cement materials.
3) DEMONSTRATION OF GAS PERMEABLE SEALS FOR RADIOACTIVE WASTE
REPOSITORIES LABORATORY AND IN-SITU EXPERIMENTS (wP-59224)
Joerg Rueedi, Paul Marschall, Nagra (Switzerland)
In low/intermediate-level waste (L/ILW) repositories, anaerobic corrosion of metals and degradation of organic materials produce
hydrogen, methane, and carbon dioxide. Gas migration in a L/ILW repository is one of the processes evaluated in the safety
assessment of deep geological disposal in low-permeability formations, in particular with respect to the development of gas pressures
in the repository caverns which could negatively affect the host rock or the engineered barrier system (EBS). In order to
restrict build-up of gas overpressures in the emplacement caverns, Nagra (National Cooperative for the Disposal of Radioactive
Waste, Switzerland) has proposed design options aimed at increasing the gas transport capacity of the backfilled underground structures,
compromising neither the low hydraulic conductivity nor the radionuclide retention capacity of the EBS (Nagra, 2008). They
involve specially designed backfill and sealing materials such as high porosity mortars as backfill materials for the emplacement
caverns and sand/bentonite (S/B) mixtures with a bentonite content of 20% to 30% for the seals themselves and for backfilling other
underground structures. These increased gas permeability materials can supplement the gas flow that is expected to occur through
the excavation damaged zone (EDZ) and avoid the creation of overpressures.
Preliminary experimental studies have confirmed the gas…
4) POST-IODINE PRODUCTION NORM REPOSITORY TECHNICAL DESIGN AND
RECONSTRUCTION EXPERIENCE IN TURKMENISTAN (wP-59183)
Alexander Gelbutovsky, Peter Cheremisin, Alexander Troshev, Alexander Egorov,
Mikhail M. Boriskin, Mikhail Bogod, ECOMET-S (Russia)
Continuous extraction of the iodine, bromine and other elements from the underground mineral waters at the Balkanabat
Iodine and Khazar chemical plants (Turkmenistan) resulted in their territories NORM contamination and significant waste quantities
formation. Sites radiation safety is the major issue. Usually there are no any radiation monitoring systems and staff providing
personnel, population and environment radiation safety and negative influence elimination. The most dangerous sites are the ones
which are situated in the Caspian Sea coastal area. In 2009 the remediation project was initiated to prevent NORM distribution and
eliminate environmental threat. The project frame covers a number of preparation and design works, charcoal sorption shops demolition,
territories remediation, production waste conditioning and transportation to the repository for further safe storage. For that
purposes the repository has been built in the near-by natural hollow. In the given report the materials related to repository design,
reconstruction and operations start are presented. The brief data on the facilities condition, contamination characteristics and waste
quantities are indicated. It is shown that that the mechanical method has been chosen for contaminated materials collecting and disposal.
Main demolition, remediation and transportation decisions, activities and results are mentioned also.
SESSION 44 — DISPOSAL SITE AND WASTE FORM CHARACTERIZATION
AND PERFORMANCE ASSESSMENT - PART 1 OF 2 (1.13)
1) RADIOLOGICAL CHARACTERIZATION OF THE DUTCH INTERIM
WASTE STORAGE FACILITY SITE (w/oP-59023)
Jeroen Welbergen, COVRA; Leo P.M. Velzen, Nuclear Research and Consultancy Group (Netherlands)
The Central Organization for Radioactive Waste (COVRA) in the Netherlands operates since 1993 in the south-west of the
Netherlands a facility for treatment of radioactive waste including interim storage buildings for HLW, LILW and NORM wastes as
calcinate and depleted uranium (U3O8 ). The site of the interim waste storage facility has a size of about 200,000 m2 and is situated
close to the Dutch nuclear power plant Borssele and a large phosphate production plant.
It is evident that the waste storage site is subjected at regular time intervals at non-intrusive radiological measurements (e.g.
dose-rate and contamination) to detect elevated radiation levels. However, these radiological measurements have not yet been performed
according to approaches as described in the Environment Radiation Site Survey Execution Manual EURSSEM or the Multi
Agency Radiation Site Survey Inspection Manual MARSSIM .
The aim of the paper is threefold, first to describe in detail the process how to apply EURSSEM and especially for fast nonintrusive
multi radiological detection techniques with control measurements. Second aim is to present and discuss the analyze
results and follow up actions. The third and last aim is to discuss the advantages and disadvantages of combining the analyze results
of fast non-intrusive measurements…
2) CLIMATE CHANGE IMPACTS ON THE DISPOSAL ENVIRONMENT:
A CLIMATE ANALOGUE APPROACH (wP-59274)
Bertrand Leterme, Dirk Mallants, SCK●CEN (Belgium)
The Belgian Agency for Radioactive Waste and Enriched Fissile Materials (ONDRAF/NIRAS) aims to develop a surface disposal
facility for L/ILW in Dessel (North-East of Belgium). The objective of this study is to provide estimates for the next few millennia
of both infiltration through the planned earth cover and groundwater recharge in the vicinity of the Dessel site. Available predictions
of future temperature and precipitation often extend until AD 2100 only (e.g. IPCC). To circumvent this data limitation,
we use existing records of climatic analogue stations deemed representative of future climates in Belgium. The following climate
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Abstracts Session 45
states are considered: DO (maritime temperate, present-day climate in Dessel), Cs/Cr (subtropical with dry summers/no rainfall seasonality),
EO (cold without permafrost) and FT (cold with permafrost). Climate data is then used in 1-D modelling of the soil-plantatmosphere
system to quantify infiltration through the earth cover and recharge to groundwater for a sequence of probable future
climate states.
Using criteria including altitude, distance to moisture source, and atmospheric circulation system, several analogue stations
were selected for each climate state Cs/Cr and EO/FT. They provided time series (30 years) of meteorological observations that
allowed calculating potential evapotranspiration and water balance components for soils overlying either the repository…
3) MINERALOGICAL ANALYSES OF OLD (78 AND 98 YEARS) CONCRETE (wP-59093)
Tomoko Ishii, Hitoshi Owada, Radioactive Waste Management Funding and Research Center;
Hiroyuki Sakamoto, Masahito Shibata, Kumi Negishi, Taiheyo Consultant Co.,Ltd. (Japan)
Because Ca-dissolution from cementitious material is thought as a source of the long-term alteration of the performance of
radioactive waste repository, much research such as dissolution test had been carried out. Those research brought some calculation
models for leaching of cementitious material such as Atkinson’s model. Those calculation models have been verified that the results
represent the alteration of cementitious minerals and the composition of the leachate by many researches. By using these calculation
models, many estimation calculation for long-term mineralogical alteration in repository, such as cementitious barrier system,
cement-clay interaction and so on, were carried out and the performance change of the repository were evaluated. However, results
of immersion test by using bulky cementitious material had often pointed out that the actual alteration of cementitious material
might be slower than the results of estimation calculation. This difference might be due to the change of mass-transport characteristics
in the bulky cementitious material and/or at interfaces with the other materials.
In this study, mineralogical analyses of two types old concretes were carried out. Drilled cores were collected from under
groundwater level of the foundations of rotary kiln of cement production factory. Both of these concrete were made from Japanese
ordinarily cement…
4) MODELING OF ALTERATION BEHAVIOR ON BLENDED CEMENTITIOUS MATERIALS (wP-59096)
Hitoshi Owada, Tomoko ISHII, Radioactive Waste Management Funding and Research Center;
Mayumi Takazawa, Hiroyasu Kato, Mitsubishi Materials Corporation;
Hiroyuki Sakamoto, Taiheyo Consultant Co.,Ltd.; Masahito Shibata, Taiheyo Consultant Co., Ltd. (Japan)
Weve been trying to set the realistic alteration model for carious cementitious materials. Imaginary settings of mineral composition
calculated by using chemical composition of cement, such as Atkinss model, had been used for the alteration calculation
of cementitious material. However, calculated values of the concentration for some elements such as Al and S in leachate had been
different from experimental values. In our previous study, we had set the mineralogical alteration model by using an allocation to
some hydrated cement minerals from an experimentally analyzed initial chemical composition of the cementictious materials, and
by the setting of secondary generated minerals that considered the leaching of Ca. As the result, the change of Al and S concentration
in simulated leachate had approached to that in actual leachate in the alteration calculation for ordinary portland cement
(OPC) in groundwater.
In this study, for development of an appropriate mineral alteration model for blended cementictious materials, batch type
leaching experiments that used the crushed sample of blast furnace slag cement and the silica cement were done. Blast furnace
slaggy cements that mixed OPC with the blast furnace slag of 70wt.% and 90wt.% were used. Similarly, the silica cement that
mixed OPC with an amorphous…
SESSION 45 — REPOSITORY PROGRAMS: SITE SELECTION & CHARACTERIZATION,
UNDERGROUND RESEARCH LABS, ENGINEERING & GEOLOGICAL BARRIERS - PART 2 OF 2 (2.7)
1) EBS BEHAVIOR IMMEDIATELY AFTER REPOSITORY CLOSURE IN A CLAY HOST ROCK:
THE HE-E EXPERIMENT (MONT TERRI URL) (wP-59288)
Irina Gaus, Nagra; Klaus Wieczorek, GRS; Juan Carlos Mayor, ENRESA; Kristof Schuster, BGR;
Thomas Trick, Solexperts; José-Luis Garcia-Siñeriz, Aitemin; Benoit Garitte, CIMNE; Uli Kuhlman,
TK Consult (Switzerland/Germany/Spain)
The evolution of the engineered barrier system (EBS) of geological repositories for radioactive waste has been the subject of
many research programmes during the last decade. The emphasis of the research activities was on the elaboration of a detailed
understanding of the complex thermo-hydro-mechanical-chemical processes, which are expected to evolve in the early post closure
period in the near field. It is important to understand the coupled THM-C processes occurring in the EBS during the early post-closure
phase so it can be confirmed that the safety functions will be fulfilled. Especially, it needs to be ensured that unexpected
process interactions during the resaturation phase (heat pulse, gas generation, non-uniform water uptake from the host rock) do not
affect the homogeneity of the safety-relevant parameters in the EBS (e.g. swelling pressure, hydraulic conductivity, diffusivity).
The 7th Framework PEBS project (Long Term Performance of Engineered Barrier Systems) is using in depth process understanding
for constraining the conceptual and parametric uncertainties in the context of long-term safety assessment. In previous EUsupported
research programmes remarkable advances have been made to broaden the scientific understanding of THM-C coupled
processes in the near field around the waste canisters. However, the detailed thermo-hydraulic behaviour of a bentonite EBS in a
clay hostrock in response to anticipated temperatures of up to 140°C, produced by HLW (and spent fuel) at the canister surface, has
so far not been evaluated at a large scale. Furthermore, earlier THM experiments have shown that upscaling of thermal conductivities
and its dependency on the water contents from the laboratory scale to a field scale needs further attention.
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Session 46 Abstracts
2) PERFORMANCE ASSESSMENT MODELING FOR THE GEOLOGICAL SITING REGIONS FOR THE L/ILW
AND HLW REPOSITORIES IN THE CONTEXT OF THE SWISS SITE SELECTION PLAN (wP-59306)
Andreas Poller, Juerg Schneider, Piet Zuidema, Nagra; Johannes Holocher,
Gerhard Mayer, AF-Consult Switzerland Ltd. (Switzerland)
In Switzerland, the Nuclear Energy Law requires the disposal of all radioactive waste in deep geological repositories. The procedure
for selecting the repository sites is defined in the Sectoral Plan for Deep Geological Repositories and consists of three stages.
In Stage 1, the National Cooperative for the Disposal of Radioactive Waste (Nagra) proposed geological siting regions based on
criteria relating to safety and engineering feasibility. As part of Stage 2, Nagra has to select at least one site within each siting region,
to carry out a provisional safety analysis for each site and a safety-based comparison of the sites. In order to achieve these objectives,
the state of knowledge of the geological conditions in the siting regions has to be sufficient to perform the provisional safety
analyses. In October 2010, Nagra published a report which documents Nagra’s technical-scientific assessment of this precondition,
based on a comprehensive list of processes and parameters relevant for safety and engineering feasibility. A part of this assessment
consists of test calculations for the provisional safety analyses. This paper summarizes how the numerous test calculations
have been identified, how the concepts of radionuclide release from the repository are implemented into numerical codes and how
input data and results are organized in order to ensure transparency and traceability.
3) INVESTIGATIONS OF THE POSSIBLE SEPARATION DISTANCE BETWEEN SPENT
FUEL/HIGH-LEVEL WASTE AND A LOW/INTERMEDIATE-LEVEL WASTE REPOSITORIES
DUE TO GAS AND HEAT GENERATION (wP-59220)
Rainer Senger, John Ewing, Intera Inc. Swiss Branch; (Switzerland)
This study is part of a generic investigation for the assessment of the required minimum distance between a Spent Fuel/High-
Level Waste/ Intermediate-Level Waste (SF/HWL/ ILW) repository and a Low/ Intermediate-Level Waste (L/ILW) repository. For
this, a large-scale numerical model was constructed to investigate the two-phase flow behavior for such a repository configuration
in a low-permeability claystone formation. The modeling focused on the pressurization mechanisms associated with (a) resaturation
of backfilled underground facilities, (b) thermal effects caused by heat generation from the SF/HLW canisters, and (c) gas generation
from corrosion and degradation of different wastes in the L/ILW and ILW caverns and in the SF/HLW emplacement tunnels.
The model accounts for gas generation from corrosion and degradation of both L/ILW and ILW wastes indicating decreasing
rates with time, and from corrosion of the SF/HLW canisters characterized by a constant rate. Heat generation from radioactive
decay of radionuclides of MOX/UO2 wastes is described by an exponential decay with time. The preceding operational phases of
the different repository components were simulated representing the transient initial conditions for the post-closure phase.
4) HYDRAULIC/MECHANICAL MODELING OF SMECTITIC MATERIALS FOR HMC ANALYTICAL
EVALUATION OF THE LONG TERM PERFORMANCE OF TRU GEOLOGICAL REPOSITORY (wP-59090)
Ichizo Kobayashi, Kajima Corporation; Hitoshi Owada,
Tomoko Ishill, Radioactive Waste Management Funding and Research Center (Japan)
Aiming at evaluation of the long term performance of TRU geological repositories, the HMC analytical method has been studied.
In this phase of the research, which is for four years, the hydraulic/mechanical modeling of smectitic materials for HMC analyses
has been studied. In this paper, especially, the new experimental methods for investigation of the hydraulic/mechanical behavior
of smectitic materials were developed.
For the hydraulic modeling, the measurement method of the specific surface area of compacted smectitic materials was developed
using XRD. The results of the method were applied to the Kozeny-Carman law. Since the specific surface area represents the
microstructure of smectitic materials such as degree of swelling, it was found that the Kozeny-Carman law using measured specific
surface area of compacted smectitic materials was useful to evaluating the hydraulic performance of smectitic materials. Moreover,
since the Kozeny-Carman law can take the alteration of content of pore water into consideration by not only a coefficient of
viscosity but also change of specific surface area, the Kozeny-Carman law will be more suitable to chemical and mechanical couple
analyses than ordinary Darcy’s law.
SESSION 46 — NATIONAL AND INTERNATIONAL PROGRAMS FOR
SPENT FUEL, FISSILE, TRU, AND HLW MANAGEMENT (2.2)
1) IMPLICATIONS OF CO-EXISTING NATIONAL AND MULTINATIONAL GEOLOGICAL
REPOSITORY DEVELOPMENT PROGRAMMES IN EUROPE (wP-59118)
Neil A. Chapman, Charles McCombie, Arius Association; Ewoud Verhoef, Covra (Switzerland/Netherlands)
The aim of this paper is to identify interactions between national and multi-national geological repository programmes that are
potentially either beneficial or problematic, so as to avoid any unintended negative impacts on national or multinational programmes
and to maximise mutual benefits wherever possible. Regional, multi-national cooperation on geological disposal is a topical
issue at present at the IAEA and also in the EU, which has produced a new proposed Directive that explicitly allows agreements
on sharing.
Two extended tables in the paper identify and comment briefly on historic and current positive and negative perceptions of coexisting
national and multinational geological disposal programmes. It would, we believe, be a positive message to the global
nuclear community to know that leading national disposal programmes are interacting constructively with regional initiatives. The
extensive experience already gained in national programmes could be very beneficial to new nuclear countries. In particular, it is
crucial for all nuclear programmes that the new entrants develop credible, long-term waste management programmes, whether these
be national, regional or dual-track. For global safety and security reasons, the nuclear community must move towards a situation
where both national and shared programmes will co-exist and interact symbiotically.
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Abstracts Session 47
2) REGULATION OF AGEING FACILITIES - THE UK REGULATORS PERSPECTIVE (wP-59353)
Ryan Maitland, Unit 2G Nuclear Installations Inspectorate (UK)
The UKs strategy for spent Magnox reactor fuel demands continued operation of the Magnox Reprocessing facility at Sellafield
(located in the North West of England) to reprocess the remaining spent fuel in the shutdown Magnox reactor stations and
fuel from the two remaining operational Magnox reactor stations, Wylfa and Oldbury. Safety, security, environmental, transport,
energy and economic issues provide the initiative to continue reprocessing in ageing facilities that are prone to chronic operational
and nuclear safety challenges. One of the responsibilities of the UKs Office for Nuclear Regulation is to regulate the safety of continuing
Magnox Reprocessing Operations against relevant health and safety legislation; this largely non-prescriptive framework
requires dutyholders to demonstrably reduce risk so far as is reasonably practicable.
This paper articulates the often complex balances that have to be made to demonstrate compliance with safety law to sustain
continued operation of ageing reprocessing facilities. This paper details how the UKs regulatory framework facilitates a flexible,
proportionate and goal-setting approach to regulating operational facilities where it is difficult to satisfy relevant good practice or
standards that would be expected of a modern facility. The challenges presented by regulation of ageing, operational facilities is
analogous to those from legacy waste retrieval and decommissioning; this paper reflects the versatility of the UKs regulatory
approach to these two different areas of the fuel cycle.
3) ESTABLISHMENT OF RESEARCH AND DEVELOPMENT PRIORITIES REGARDING
THE GEOLOGIC DISPOSAL OF NUCLEAR WASTE IN THE UNITED STATES AND
STRATEGIES FOR INTERNATIONAL COLLABORATION (wP-59168)
Mark Nutt, Argonne National Laboratory; Michael Voegele, Complex Systems LLC; Jens Birkholzer,
Lawrence Berkeley National Laboratory; Peter Swift, Sandia National Laboratories;
Jeff Williams, U.S. Department of Energy; Kevin McMahon, Sandia National Laboratories;
Mark Peters, Argonne National Laboratory (USA)
The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technologies (OFCT) has established
the Used Fuel Disposition Campaign (UFDC) to conduct research and development (R&D) activities related to storage,
transportation and disposal of used nuclear fuel (UNF) and high level radioactive waste (HLW).
The U.S. has, in accordance with the U.S. Nuclear Waste Policy Act (as amended), focused efforts for the past twenty-plus
years on disposing of UNF and HLW in a geologic repository at Yucca Mountain, Nevada. The recent decision by the U.S. DOE
to no longer pursue the development of that repository has necessitated investigating alternative concepts for the disposal of UNF
and HLW that exists today and that could be generated under future fuel cycles. The disposal of UNF and HLW in a range of geologic
media has been investigated internationally. Considerable progress has been made by in the U.S and other nations, but gaps
in knowledge still exist.
The U.S. national laboratories have participated in these programs and have conducted R&D related to these issues to a limited
extent. However, a comprehensive R&D program investigating a variety of storage, geologic media, and disposal concepts has
not been a part of the U.S. waste management program since the mid 1980s because of its focus on the Yucca Mountain site. Such
a comprehensive R&D program is being developed and executed in the UFDC using a systematic approach to identify potential
R&D opportunities. This paper describes the process used by the UFDC to identify and prioritize R&D opportunities.
4) THE CIGÉO GEOLOGICAL REPOSITORY PROJECT (wP-59265)
Thibaud Labalette, Alain Harman, Marie-Claude Dupuis, Andra (France)
The future industrial geological repository Cigéo will provide France with a long term safe management solution for high level
and long-lived intermediate waste produced by the French nuclear industry. According to the French Act of 28 June 2006, Andra
carries out design studies so that the application can be examined in 2015 and, subject to licensing, the facility can be operated in
2025.
To be successful, the project must address issues related to local integration, industrial planning, safety and reversibility, while
controlling costs. Andra is the guarantor of the balance between these concerns.
A significant project milestone was reached in 2009 with the definition of an area of interest to locate the underground repository
facilities. A new phase of dialogue with local actors is being performed to precise implementation scenarios of surface facilities.
The site selection will be approved after a public debate planned for late 2012-early 2013.
Cigéo will be an atypical nuclear facility, built and operated on over a hundred years. This long duration leads to develop repository
facilities in successive operational phases. The characteristics of the first delivered waste packages will determine the investments
by 2025 on the repository site as well as on waste production and interim storage sites.
The underground repository facilities include specific features that cannot be simply transposed from current nuclear industry
practices such as the co-activity between mining and nuclear operations, the ventilation and the fire risk management.
SESSION 47 — RADIUM REMEDIATION HISTORICAL PERSPECTIVES
AND CURRENT CIRCUMSTANCES - PART 2 OF 3 (4.47)
1) PORT RADIUM START TO FINISH LIFE CYCLE: A CASE STUDY ON CANADA’S
HISTORIC RADIUM/URANIUM MINE, INITIAL OPERATION AND CLOSURE, CONCERNS OF
THE ABORIGINAL DENE PEOPLE, SUBSEQUENT ASSESSMENTS, REMEDIATION (wP-59332)
Gerd Wiatzka, SENES Consultants Ltd. (Canada)
Presentation by Steve Brown, SENES Consultants Ltd (USA)
This paper provides a life study cycle case study on the historic Port Radium mine. In addition to the history of operations, it
discusses the unique and successful approach used to identify the key issues and concerns associated with the former radium, uranium
and silver mining property and the program activities undertaken to define the remedial issues and options that ultimately lead
to the development of a preferred remedial plan. The Port Radium Mine site, situated approximately 275 km north of Yellowknife
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Session 47 Abstracts
on the east shore of Great Bear Lake, Northwest Territories, was operated almost continuously between 1932 and 1982, initially for
recovery of radium and uranium and subsequently for recovery of silver. Tailings production equalled an estimated 900,000 tons
from uranium ore processing and 800,000 tons from silver processing operations. While the site was decommissioned at mine closure,
site investigations were undertaken to address concerns expressed by residents of the community of Déline about residual contamination
at the site and exposure of Déline residents as traditional land users and to identify residual environmental and safety
issues based on current closure standards. Assessment of past radiation exposures of worker based on past practices associated with
ore handling and concentrate shipping were also addressed. The paper provides insights into the approach and activities undertaken
over a seven (7) year period that ultimately concluded with the final decommissioning of the site in 2007 and post remedial
actions being carried out under the long term care and maintenance program.
2) CHALLENGES IN DEVELOPING A REMEDIATION PLAN, PROCUREMENT PLAN
AND LONG TERM MONITORING PROGRAM FOR THE FORMER PORT RADIUM URANIUM
MINE THAT MEETS THE NEEDS OF THE COMMUNITY OF DELINE (w/oP-59333)
Julie Ward, Indian and Northern Affairs Canada (Canada)
After a five year political process to investigate historic and present day concerns about the former Port Radium Uranium Mine,
the site has being remediated to present day standards. Prior to remediation Indian and Northern Affairs Canada (INAC) worked
with Deline First Nations to develop a Remediation Plan that was suitable to the known environmental conditions and identified
risks on site. Prior to remediation INAC obtained a land use permit and Waste Nuclear Substance Licence for the work that was
carried out and for future storage of radioactive wastes. After the remediation plan was complete a procurement plan was developed
for the work which followed Federal contracting polices, met the intent of the Sahtu Dene and Metis Comprehensive Land
Claim Agreement and abided by INACs commitment under the Canada Deline Uranium Table to maximize local participation and
subcontracting opportunities. Lastly, INAC worked with Deline to develop a monitoring plan in hopes to begin to restore their confidence
in their environment while monitoring engineered remedial structures and residual risks on site.
3) OVERVIEW OF RADIUM LEGACIES IN BELGIUM (wP-59367)
Stephane Pepin, Koen Mannaerts, Boris Dehandschutter, André Poffijn, Ludo Jadoul,
Walter Blommaert, Michel Sonck, FANC (Belgium)
The Belgian metallurgical company, Union Minière, has been a key-player in the sector of radium production between 1922
and 1969. The factory based in Olen has extracted radium from minerals and produced radium sources during that period. The radium
production facilities have been dismantled in the 70s but legacies of the former production have still to be remediated. An
overview of these legacies and of their radiological characteristics will be given.
Next to the sites related to radium production, other radium legacies are related to NORM industries, essentially from the phosphate
sector (phosphogypsum and CaF2 stacks).
4) PREPARING FOR THE CONSTRUCTION PHASE OF THE PORT HOPE AREA INITIATIVE:
CANADA’S LARGEST LOW-LEVEL RADIOACTIVE WASTE CLEAN-UP PROJECT (wP-59307)
Christine Fahey, Andrea Denby, Glenn Case, Atomic Energy of Canada Ltd.;
Tim Palmeter, Public Works Government Services Canada (Canada)
The Port Hope Area Initiative (PHAI) is the largest clean-up of low-level radioactive waste (LLRW) ever undertaken in Canada.
Situated within two adjacent Ontario municipalities, Port Hope and Clarington, the project scope includes the remediation of
an estimated 1.7 million cubic metres (m3) of contaminated material and its consolidation within two new local waste management
facilities in the form of above-ground, engineered containment mounds. The waste is primarily the by-product of uranium and radium
ore processing activities of the former crown corporation Eldorado Nuclear Limited between 1932 and 1988.
The PHAI is sponsored by the Government of Canada under the federal historic liabilities management program that is the
responsibility of Natural Resources Canada (NRCan). Following the development of a new project execution framework in 2008,
the PHAI Management Office, consisting of Atomic Energy of Canada Limited (AECL), Public Works & Government Services
Canada (PWGSC) and NRCan staff, was established to perform the majority of Canadas obligations for the clean-up.
The terms of reference for the PHAI are set out in a Legal Agreement signed in 2001 between the Government of Canada and
the host municipalities. The Legal Agreement outlines a three-phased approach for the implementation of the PHAI:
Phase 1 - planning and regulatory approvals; Phase 2 - remediation and construction; and Phase 3 - long-term monitoring and
maintenance.
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Abstracts Session 48
SESSION 48 — PANEL: RADIUM REMEDIATION - HISTORICAL PERSPECTIVES
AND CURRENT CIRCUMSTANCES - PART 3 OF 3 (4.13)
ABSTRACTS NOT REQUIRED
SESSION 49 — PANEL: COMMUNICATIONS AND KNOWLEDGE MANAGEMENT - PART 1 OF 2 (5-21)
ABSTRACTS NOT REQUIRED
SESSION 50 — PANEL: COMMUNICATIONS AND KNOWLEDGE MANAGEMENT - PART 2 OF 2 (5-21)
ABSTRACTS NOT REQUIRED
SESSION 51 — SAFETY CONSIDERATIONS ASSOCIATED WITH L/ILW MANAGEMENT (1.14)
1) UK LLWR ENVIRONMENTAL SAFETY CASE SUBMISSION 2011 (wP-59135)
Richard Cummings, LLWR Ltd; Andrew Baker, LLWR; Trevor Sumerling, LLWR;
John Shevelan, Amy Huntington, LLWR Ltd. (UK)
The UK’s Low Level Waste Repository Ltd submitted an Environmental Safety Case (ESC) for the disposal of low-level waste
to the Environment Agency on the 1st of May 2011. The ESC is a major submission that will decide the future use of the Repository
and has major implications for the success of the UK’s LLW Strategy and decommissioning programme. This paper provides
an overview of the work that has been carried out to support the submission.
Key aspects of this ESC include:
detailed investigations of existing disposals, based on careful examination of existing records and other investigations, including
interviews with former operational staff; analysis of uncertainties in future disposals; modelling of the biogeochemical evolution
of the disposal system, which provides understanding of the evolution of pH, Eh and gas generation and thence underpinning
for radionuclide releases in groundwater and gas; development of a 3-D groundwater flow model, calibrated against observed heads
and with a detailed representation of the engineered features; analysis of coastal erosion and its impacts; a major focus on optimisation
based on detailed technical studies; a conclusion that existing disposals do not require remediation; the choice of a concrete
vault design with permeable side walls designed to avoid bathtubbing after the end of management control; a comprehensive set of
assessment calculations, including thorough analysis of uncertainties, which demonstrate consistency with the Environment
Agency’s risk and dose guidance levels; revision of the LLWR’s WAC, based in part on the use of the ‘sum of fractions’ approach;
the use of a safety case document structure that emphasises key safety arguments in a Level 1 document and provides supporting
evidence in a series of Level 2 documents; the provision of a Level 2 document that describes in detail how each aspect of the regulatory
guidance has been addressed.
2) AN ASSESSMENT OF THE RADIOLOGICAL IMPACT OF COASTAL EROSION
OF THE UK LOW-LEVEL WASTE REPOSITORY (wP-59137)
Trevor Sumerling, LLWR; Paul Fish, Halcrow Ltd.; George Towler, James Penfold, Quintessa Ltd;
John Shevelan, Richard Cummings, LLWR Ltd. (UK)
The UK Low Level Waste Repository Ltd submitted an Environmental Safety Case for the disposal of low-level waste to our
regulator, the Environment Agency, on the 1st of May 2011. This includes assessments of the long-term radiological safety of past
and future disposals.
A particular feature of the Low Level Waste Repository (LLWR) is that, because of its proximity to the coast, the site is vulnerable
to coastal erosion. Our present understanding is that the site will be eroded on a timescale of a few hundred to a few thousand
years, with consequent disruption of the repository, and dispersal of the wastes.
We have undertaken a programme of scientific research and monitoring to characterise the evolution and function of the current
coastal system that provides a basis for forecasting its future evolution. This has included modelling of contemporary hydrodynamics,
geomorphological mapping, repeat LiDAR and aerial photographic surveys to detect patterns and rates of change, coastal
inspections and reconstructions of post-glacial (i.e. last 15,000 years) sea levels and sediment budgets. Estimates of future sealevel
rise have been derived from international sources and consideration given to the impact of such on the local coastline. Two
alternative models of coastal recession have then been applied, one empirical and one physical-process based, taking account of the
composition of Quaternary-age sediments between the coast and the site and uncertainties in future local sea level change.
3) DEVELOPMENT OF A METHODOLOGY FOR DETERMINING ILW PACKAGE
MONITORING AND INSPECTION REQUIREMENTS (wP-59156)
Jenny E. Morris, Timothy W. Hicks, Stephen M. Wickham, Galson Sciences Limited;
Antonio Guida, Babcock International Group; Melanie Brownridge, James McKinney
Darrell Morris, Nuclear Decommissioning Authority; Mark Tearle, Magnox Limited (UK)
In the UK, monitoring and inspection is required by the regulators to ensure continued safe storage, retrievability and disposability
of packages of radioactive waste in interim storage. Monitoring and inspection requirements may also be determined by any
requirements for transport, further storage or disposal when the store is emptied. This paper presents an approach to establishing
a monitoring and inspection strategy for stored intermediate level waste (ILW) packages that was developed under the UK Nuclear
Decommissioning Authoritys Direct Research Portfolio programme.
The key aspects to be considered when developing a package monitoring and inspection strategy are identified and used to
develop a generic multi-stage process that will enable store operators to identify a justifiable monitoring and inspection strategy for
ILW packages in long-term interim storage. Two spreadsheet tools have also been developed to facilitate use of the multi-stage
process by store operators (IMPS - Inspection and Monitoring of Packages in Stores and CBAT - Cost / Benefit Analysis Tool).
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Session 51 Abstracts
A statistically based methodology has been used to identify the number of waste packages to be inspected and an appropriate
frequency of inspection, and aspects such as cost, risk and operational feasibility are taken into account.
4) AN ASSESSMENT OF THE RADIOLOGICAL IMPACT OF HUMAN INTRUSION
AT THE UK LOW LEVEL WASTE REPOSITORY (LLWR) (wP-59356)
Timothy Hicks, Tamara Baldwin, Galson Sciences Ltd; Richard Cummings, LLWR Ltd.; Trevor Sumerling, LLWR (UK)
The UK Low Level Waste Repository Ltd submitted an Environmental Safety Case for the disposal of low level waste (LLW)
to the Environment Agency on the 1st of May 2011. The Environmental Safety Case (ESC) presents a complete case for the environmental
safety of the Low Level Waste Repository (LLWR) both during operations and in the long term (Cummings et al, in these
proceedings). This includes an assessment of the long-term radiological safety of the facility, including an assessment of the potential
consequences of human intrusion at the site.
The human intrusion assessment is based on a cautiously realistic approach in defining intrusion cases and parameter values.
A range of possible human intrusion events was considered based on present-day technologies and credible future uses of the site.
This process resulted in the identification of geotechnical investigations, a housing development and a smallholding as requiring
quantitative assessment.
A particular feature of the site is that, because of its proximity to the coast and in view of expected global sea level rise, it is
vulnerable to coastal erosion. During such erosion, wastes and engineered barrier materials will be exposed, and could become targets
for investigation or recovery. Therefore, human intrusion events have been included that are associated with such activities.
5) FACTORS AFFECTING THE LONGEVITY OF INTERIM ILW STORES, MONITORING METHODS
AND TECHNIQUES SUPPORTING STORE LIFE EXTENSION (wP-59151)
Jenny E. Morris, Stephen Wickham, Timothy Hicks, Phil J. Richardson, Galson Sciences Limited; Melanie Brownridge,
Darrell Morris, James McKinney, Nuclear Decommissioning Authority; Mark Tearle, Magnox Limited (UK)
Life-limiting features of stores (i.e. components of a typical Intermediate Level Waste (ILW) store that are vulnerable to failure)
can be separated into those related to store design, the continuing operation of the store and equipment and store management.
Environmental factors, including temperature, humidity, atmospheric pollutants and radiation fields also affect the longevity of ILW
storage buildings and the integrity of the waste packages within the store.
The current condition of the store and the causes and rates of any observed deterioration need to be determined to estimate the
current operating life of the store and to analyse the costs and benefits associated with life extension.
Suitable monitoring techniques and methods for extending the operating life of stores, either by remediation or replacement of
identified life-limiting features, have also been assessed. Techniques including visual inspection (directly or by use of CCTV or
inspection cells), corrosion coupons, crane monitoring and a wide range of indirect measurement methods can be used to monitor
the condition of life-limiting features and the store environment. Methods for extending store life include the application of paint
or coatings to retard degradation, use of electro-chemical treatments and repair of the concrete structure or replacement of components.
6) DIFFERENT TYPES OF RADIOACTIVE WASTE REPOSITORIES, EACH SUITED
FOR A GIVEN TYPE OF RADIOACTIVE WASTE (wP-59293)
Sylvie Voinis, Fabrice Boissier, Lise Griffault, Jean Louis Maillard, Michel Dutzer, Andra (France)
The aim of this article is to present how Andra implements a dedicated solution per waste category. It relies on response to a
series of questions concerning the appropriate waste disposal system such as: What type of radiological inventory is involved?
What are the half-lives of the radionuclides and the associated timescales concerned for achieving the fundamental protection objective?
.
In that respect, Andra has developed and has implemented methods for all disposal facilities in order to reach common objectives:
The immediate and long term protections of human beings and the environment constitute the fundamental objectives of all
radioactive-waste disposal facilities.
In order to achieve those protections, disposal facilities must be safe. Thus, Andra safety encompasses all design, implementation
and operational measures for preventing risks of all kind internal, external during operation and after closure in consistency
with defence in depth principles taken into account the peculiarity of waste disposal facilities: (i) balancing operational safety and
post-closure safety, (ii) management of nuclear risks in underground repository for some of them, (iii) management of scientific
understanding and related uncertainties, and (iv) management of long or very long- timescales.
The presentation will illustrate Andras approach that has or will be conducted and will focus on communalities or peculiarities
according to the type of waste and related disposal options regarding the following iterative steps: regulatory safety rules, input
data, scenarios, safety assessments.
SESSION 52 — DISPOSAL SITE AND WASTE FORM CHARACTERIZATION
AND PERFORMANCE ASSESSMENT - PART 2 OF 2 (1.20)
1) CHARACTERISATION OF THE GEOLOGY OF THE UK LOW LEVEL WASTE REPOSITORY (wP-59146)
John Shevelan, LLWR Ltd; Nicholas Smith, National Nuclear Laboratory (UK)
The UK Low Level Waste Repository Ltd (LLWR) submitted an Environmental Safety Case (ESC) for the disposal of lowlevel
waste (LLW) to the UK Environment Agency on the 1st of May 2011. As part of the ESC, the LLWR have to demonstrate
that a programme of site investigation and site characterisation has been carried out to provide the requisite information for the ESC
and support facility design and construction. This paper explains the development of the site investigation programme and how the
understanding of the geology of the site has developed.
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Abstracts Session 52
The geological environment in the region of the LLWR consists of Quaternary age deposits overlying older bedrock. The site
has been subjected to a series of site investigation programmes from 1939 to the present day. The development of 3-D geological
models was necessary to integrate data from boreholes, trial pits, geophysical investigations and beach exposures and data gained
from site operations.
The understanding of the geology has developed with each new set of data. Early simple interpretations from a few boreholes
have been superseded by a series of more complex interpretations each incorporating the increasingly detailed observations. Initial
attempts to develop a lithostratigraphic representation of the geology proved difficult. It was also difficult provide a clear link
between the geology and the hydrogeology using a lithostratigraphic approach as required for the development of hydrogeological
models.
2) IN-SITU INTERFEROMETRIC MEASUREMENTS OF COMPACTED SMECTITE
UNDER HYPERALKALINE CONDITION (w/oP-59124)
Hisao Satoh, Susumu Kurosawa, Mitsubishi Materials Corporation; Tomoko Ishii,
Hitoshi Owada, Radioactive Waste Management Funding and Research Center (Japan)
Alteration of bentonite buffer at the repository for radioactive waste is an unavoidable phenomenon. However, precise kinetic
data is useful for evaluation of the endurance for long-term safety. Alkaline attack to bentonite by cement-leachates may enhance
alteration of smectite into the other phase such as zeolite. Until recently, there are a number of detailed dissolution studies (e.g.,
Cama et al., 2000; Yokoyama et al., 2005; Rozalen et al., 2008) for suspended smectite, using high precision measurements by ICP-
MS and AFM analyses. In contrast, dissolution study of compacted smectite is very limited (e.g., Nakayama et al., 2003). In order
to verify the previous data, the dissolution rate of compacted smectite with realistic density needs to be confirmed experimentally.
We have, for the first time, applied in-situ vertical scanning interferometry (VSI) along with the auto-compaction cell for measuring
dissolution rates of smectite compacted at 0.04-20.0 MPa and 70 ̊C in 0.3 M NaOH (pH12.1).
At less-compaction (0.04 MPa), Kunipia-P smectite initially showed a relatively fast dissolution of ~2E-11 mol/m2/s which is
comparable to the rate for suspended smectite under same pH-T condition. At high-compaction (

Session 53 Abstracts
design, closure design, and quantitative assessments. Each of these issues requires an understanding of the movement of water
through the facility and the surrounding geology during operations and following facility closure. Groundwater flow modelling has
been used extensively in support of interpretation of field investigations, development of vault design, and assessment of the
groundwater pathway as one of the major pathways by which contaminants may reach the environment. This paper describes these
important aspects of the Environmental Safety Case.
SESSION 53 — GLOBAL PARTNERSHIPS AND NATIONAL INITIATIVES IN
ENVIRONMENTAL MANAGEMENT - PART 1 OF 2 (5.13)
1) RUSSIAN NUCLEAR SUBMARINE ELIMINATION 2001 - 2011 BY THE
INTERNATIONAL COMMUNITY (w/oP-59041)
Michael Washer, Foreign Affairs and International Trade Canada; Alan Heyes, King’s College (Canada/UK)
Following the 911 attack on the USA in 2001 the international community under Canadas G8 leadership established a $20 billion
Global Partnership initiative to collaboratively address threats to global security posed by the proliferation and potential terrorist
use of Weapons and Materials of Mass Destruction (WMMD) and related materials and knowledge. As an integral component
of this initiative the international community agreed to assist Russia in advancing the elimination of its Cold War legacy of
nearly 200 nuclear powered submarines left over from the collapse of the Soviet Union. This presentation presents an overview of
the 10 years work that has now entirely eliminated that submarine legacy. The scale and complexity of the challenge along with
each countrys contribution and approach is discussed along with key success factors and unique solutions adopted.
2) THE GLOBAL PARTNERSHIP: ITS ACHIEVEMENTS, MISSED OPPORTUNITIES AND POTENTIAL TO
ADDRESS FUTURE THREATS FROM THE SPREAD OF CBRN MATERIALS AND EXPERTISE (w/oP-59335)
Alan Heyes, Wyn Bowen, Hugh Chalmers, King’s College (UK)
In 2002, the G8 launched the Global Partnership (GP) against the Spread of Weapons and Materials of Mass Destruction. The
partnerships budget was placed at $20 billion over 10 years, and it was supported by some 23 countries and the European Union
(EU).Though it has had little public recognition, the partnership has been one of the G8s most successful initiatives and has led to
many benefits, including improved international security and addressing a sizeable proportion of the Cold War nuclear and chemical
weapons arsenal in the Former Soviet Union. Its future, however, remains undecided, as its funding is set to expire in less than
two years.
In 2009 and 2010 Kings College London with generous funding support from the US John D and Catherine T MacArthur
Foundation, carried out a detailed evaluation of the achievements and benefits of the GP to date, its failings and lost opportunities,
and potential future direction. Our findings indicate that the partnership has aided security in the Former Soviet Union and had a
significant number of wider benefits with the potential to continue to do the same on a broader geographic level in future. As such,
it is a valuable tool to assist the international community to work together to address global threats relating to chemical, biological,
radiological and nuclear materials and related expertise and the G8 should take steps to renew its funding.
3) THE GLOBAL THREAT REDUCTION INITIATIVES RADIOLOGICAL
SECURITY COOPERATION WITH RUSSIA (wP-59361)
Tiffany Blanchard, U.S. Department of Energy/National Nuclear Security Administration;
William Abramson, Lawrence Livermore National Laboratory; James W. (J.R.) Russell, National Security Technologies;
Catherine Roberts, Pacific Northwest National Laboratory (USA)
The United States (U.S.) Department of Energy (DOE)/National Nuclear Security Administrations (NNSA) Global Threat
Reduction Initiative (GTRI) supports both U.S. and international threat reduction goals by securing vulnerable nuclear and radiological
material located at civilian sites throughout the world. GTRIs approach to reducing the threat posed by vulnerable, highactivity
radioactive sources includes: removing and disposing of orphan or disused radioactive sources; implementing physical
security upgrades at civilian sites containing radioactive sources; and establishing a cooperative sustainability program at sites to
ensure that upgrades are maintained. For many years GTRI has collaborated successfully with the Russian Federation and international
partners to improve radiological security in Russia. This paper provides a synopsis of GTRIs accomplishments and cooperation
with Russia in the following areas: 1.) recovering and disposing of orphan and disused radioactive sources, 2.) recovering
and disposing of radioisotope thermoelectric generators (RTGs), and 3.) providing physical security upgrades at civilian sites that
contain vulnerable radiological material.
4) KOLA PENINSULA RADWASTE MANAGEMENT IN THE FRAMEWORK OF THE ITALIAN-RUSSIAN
COOPERATION AGREEMENT FOR GLOBAL PARTNERSHIP (wP-59392)
Massimiliano Nobile, SOGIN (Russia)
On the 5th of November 2003 a Cooperation Agreement, envisaging a grant of 360 Meuro in 10 years, was signed in Rome
between Italy and Russia in the framework of Global Partnership Program launched by G8 at Kananaskis (Canada) in 2002. Funds
availability was assured in March 2006.
Competent Organizations are the Ministry of Economic Development for Italy and Rosatom for Russia. They act through a
Steering Committee and a Project Management Unit, based in Moscow.
So far, in five years of concrete work, 33 contracts have been signed and 145 Meuro have been spent.
Together with other significant lines of activities, e.g. nuclear submarine dismantling, the management of waste, presently
located at Andreeva Bay site, is surely the most important, not only for the amount of allocated funds (about half of available ones)
but also for the urgency to solve serious environmental problems linked to the actual unsafe conditions of these waste, both as
regards possible incidents and malicious attacks from outside.
Volume of LL/IL waste at Andreeva Bay site are 17000 tons and 3000 tons, respectively for solid and liquid; moreover is
expected, during the next 15 years, the production of additional 33000 tons of liquid and 8000 tons of solid, due to the need of
demolishing existing facilities and final closing of the site.
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Abstracts Session 54
5) SECURING OF THE SPENT NUCLEAR FUEL STORED ON GREMIKHA SITE - THE
FORMER SOVIET SUBMARINE BASE IN NORTH-WEST OF RUSSIA (w/oP-59371)
Alexandre Gorbatchev, CEA; Lucien Pillette-Cousin, AREVA TA: Boris Stepennov, NRC KI;
Valery Eremenko, SevRAO; Anatoly Zakharchev, ROSATOM (France/Russia)
In the framework of the G8 Global Partnership the French Commission on Atomic Energy (CEA) is in charge of the French
funded projects aimed to secure the materials susceptible to be a subject of the proliferation or a malicious use. The securing of the
Spent Nuclear Fuel (SNF) from the former soviet submarines is of a special importance for CEA and the Russian Rosatom. Our
main bilateral project has focused on two kinds of the SNF (alpha cores and VVR assemblies) stored at Gremikha, the former submarine
base in the North-West of Russia. As of 2011 a significant results have been achieved: 2/3 of VVR type assemblies have
been removed from Gremikha and reprocessed at PO Mayak. Nine alpha cores are unloaded and stored on at Gremikha. The main
task now is to prepare the removal from Gremikha of all the remaining SNF and also to set up the needed infrastructure at the sites
where this SNF will be moved. Substantial funding and technical assistance both from France and Russia will be required for that.
Beyond the operator of the Gremikha site (SevRAO), the CEA and Rosatom involve many expert organizations from both countries
such as AREVA, Kurchatov Institute and many others. Their contribution is one of the key elements of the success.
SESSION 54 — GLOBAL PARTNERSHIP IN ENVIRONMENTAL MANAGEMENT - PART 2 OF 2 (5.20)
1) ENVIRONMENTAL AND RADIOLOGICAL REMEDIATION UNDER CANADA’S
GLOBAL PARTNERSHIP PROGRAM 2004-11 (wP - 59185)
Michael J. Washer, Foreign Affairs and International Trade Canada (Canada)
Following the 911 attack on the USA in 2001 the international community under Canadas G8 leadership established a $20 billion
Global Partnership initiative in 2002 to collaboratively address threats to global security posed by the proliferation and potential
terrorist use of Weapons and Materials of Mass Destruction (WMMD) and related materials and knowledge. This major international
initiative addressed four priority areas (1) Chemical Weapon Destruction (2) Nuclear powered submarine eliminations (3)
Nuclear and radiological security; and (4) Employment for former weapon scientists. Additionally the Global Partnership initiative
has addressed Biological Non-Proliferation. Canadas execution of all these program areas has resulted in substantial environmental
benefits aside from the eradication and securing of WMMD. This paper will review specific environmental and radiological
remediation achievements of all Global Partnership program areas addressed under Canadian funding 2004 through 2011.
2) UK CONTRIBUTIONS TO THE DECOMMISSIONING OF THE BN-350
REACTOR IN KAZAKHSTAN: 2002 – 2011 (wP-59099)
Steven Laws, Department of Energy and Climate Change (UK), David Wells and Andrew Herrick, Nuvia Limited (UK)
Since 2002, the UKs Global Threat Reduction Programme managed by the Department of Energy and Climate Change has provided
assistance to the Republic of Kazakhstan with the decommissioning of the BN-350 sodium cooled fast reactor. Assistance
has focused on non-proliferation, safety and security projects to ensure the permanent and irreversible shutdown of the reactor and
the reduction of security, safety and environmental hazards, particularly those associated with the large inventory of liquid metal
coolants (sodium and sodium-potassium alloy) and the presence of spent nuclear fuel (SNF). UK assistance efforts have been coordinated
with those of the USA and have made use of the UKs experience in decommissioning its own fast reactor power stations,
the Dounreay Fast Reactor (DFR) and the Prototype Fast Reactor (PFR).
The paper describes work undertaken with UK technical and funding assistance support in the following areas:
• Provision of training and technical support in project management and technical topics, including assistance with finalisation
of the BN-350 Decommissioning Plan.
• Liquid metal coolant treatment projects, including immobilisation of liquid products from the Sodium Processing Facility
and processing of residual sodium remaining within the drained coolant circuits.
• Immobilisation of highly active caesium traps, arising from sodium clean-up both during reactor operations and post-shutdown.
• Operations to transfer the entire inventory of spent nuclear fuel from the reactor storage pond into dual-use storage and
transport casks and then consign these casks to long-term secure storage remote from the reactor site. This activity was
part of the major US-Kazakhstan SNF Storage Project.
• Surveys of spent fuel route facilities to establish the absence of any significant amount of nuclear material.
3) DISMANTLING OF CIVILIAN NUCLEAR POWERED FLEET TECHNICAL
SUPPORT VESSELS. ENGINEERING SOLUTIONS (wP-59386)
Konstantin Kulikov, Rinat Nizamutdinov, NIPTB Onega OAO (Russia)
At the present time six nuclear technical support ships are under supervision of Atomflot FGUP. Two of them (Volodarsky
FTB and Lepse FTB) were decommissioned and are berthing. One more ship Lotta FTB should be decommissioned during next
two years.
The nuclear technological support ships carrying SNF and radwastes appear to be a possible radiation contamination of Murmansk
region and Kola Bay because the Ship long-term storage afloat has the negative effect on hull’s structures technical condition.
As a result of this in the context of the Federal Program Nuclear and Radiation Safety (2008-2015) NIPTB Onega was engaged
by state corporation Rosatom to develop the dismantling procedure for Volodarsky FTB and Lotta FTB.
Developing of nuclear technological support ships dismantling projects the technical and economic assessment of dismantling
was carried out. The following variants were examined: formation of SRW module for long-term storage at Saida Bay; complete
dismantlement and allocation of all generated SRW into certified protective containers. The report contains description of variants,
research procedure, comparative analysis of variants of dismantling of nuclear technological support ships with dismantling of
nuclear submarine and propositions concerning further research of specified problem.
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4) PROGRESS IN INTERNATIONAL COOPERATION ON REGULATORY OF LEGACY MANAGEMENT:
EXPERIENCE IN NORWEGIAN COOPERATION PROGRAMMES (wP-59399)
Malgorzata Sneve, Norwegian Radiation Protection Authority (Norway)
This paper describes the Norwegian Radiation Protection Authoritys (NRPA) experience in regulatory cooperation projects in
Russia, with special focus on legacy issues. These legacies include many different kinds of objects and activities: obsolete large
waste sources, such as those used in radioisotope thermoelectric generators; remediation of former military sites used for storage
of spent nuclear fuel and radioactive waste; and wastes from uranium mining and ore processing. The objectives of these bi-lateral
cooperation programmes are to promote effective and efficient regulatory supervision, taking into account international recommendations
and good practice in other countries. Specific projects in the program address specific challenges which require practical
local interpretation of ICRP recommendations, the IAEA Basic Safety Standards and other IAEA requirements and guidance
documents. In some cases, new regulatory documentation has been required, as well as new regulatory procedures. In the long term,
the program is intended to lead to an enhanced and enduring safety culture. The positive experience in Russia has encouraged the
Norwegian government to extend the regulatory collaboration programme to countries in central Asia, using experience gained with
Russian regulatory authorities as well as support from Russian Technical Support Organisations. The programmes are evolving into
a regional regulatory support group. Noting this experience, the paper includes suggestions and ideas for how such regional groups
can be effective in addressing common radiation safety objectives while addressing local differences in technical, geographical,
economic and cultural matters in each country...
5) METHODOLOGICAL AND PRACTICAL BASES OF PROVIDING INFORMATION SUPPORT TO
ACTIVITIES ON ENVIRONMENTAL REMEDIATION OF THE SPENT NUCLEAR FUEL AND
RADIOACTIVE WASTE TEMPORARY STORAGE FACILITY IN GREMIKHA (wP-59375)
Dmitry Stepennov, Anatoly P. Varnavin, NRC Kurchatov Institute; Anatoly A. Zakharchev, Rosatom;
Lucien Pillette-Cousin, AREVA TA (Russia/France)
Remediation of a spent nuclear fuel (SNF) and radioactive waste (RW) temporary storage facility is a multifaceted process that
includes a number of stages, such as development of a remediation programme, performance of comprehensive engineering and
radiological survey, development of a remediation design, removal of SNF and RW up to the site cleanup. At any stage of the remediation,
making of justified decisions is ensured by availability and completeness of associated information. Huge amount of information
has to be managed. Therefore an information analysis system (IAS) was developed by the National Research Centre «Kurchatov
Institute» within the framework of the project for environmental remediation of the SNF and RW temporary storage facility
in Gremikha with financial and technical support provided by France (CEA) and the Russian Federation (Rosatom). The IAS
accumulates all information about the project: technical and radiological characteristics of objects/facilities, cartographic information,
documentation, data on the project participants, technologies and equipment involved. The IAS architecture includes the following
functional subsystems: data management, data analytical processing, project management, geoinformation, 3D modeling,
and public information. The IAS allows developers and performers of environmental remediation of the SNF and RW temporary
storage facility in Gremikha to fulfill tasks arising at all stages of the work. The IAS operating experience can be transferred for
use during surveys and remediation of any radiation hazardous facilities.
SESSION 55 — SAFETY AND SECURITY RELATED TO ENVIRONMENTAL
AND NUCLEAR MATERIALS MANAGEMENT (5.11)
1) REMOTE RADIATION AND VISUAL SURVEYS OF THE HOT CELL WASTE VAULT
AND SPENT FUEL TRANSFER ROUTE AT KAZAKHSTANS BN-350 REACTOR (wP-59101)
David Wells, Nuvia Limited, Dorchester,United Kingdom, Collin Knight, Idaho National Laboratory;
Alexander Klepikov, Nuclear Technology Safety Center; Igor Yakovlev, CRT&TD MAEC-Kazatomprom LLP;
Evgeniy Tur, National Nuclear Center of the Republic of Kazakhstan; Andrew Herrick, Nuvia Limited (USA/Kazakhatan/UK)
Kazakhstans BN-350 fast reactor was shut down in 1999 and is in the process of being decommissioned in preparation for Safestore.
A key achievement during 2010 was the removal of the known inventory of spent nuclear fuel (SNF) from the reactor to offsite
secure storage. As a complementary activity, surveys of areas of the fuel discharge route where it was considered possible for
fuel pins or fuel residues to have collected over many years of operation were also arranged to confirm that no significant amounts
of fuel of remained at the plant.
This paper reports on the remote radiation and visual (video and still photograph) surveys undertaken on the following areas
of the spent fuel route:
• The waste storage repository or vault underneath the Post-Irradiation Examination Hot Cell in which non-destructive and
destructive examination of irradiated fuels was undertaken throughout the operating life of the reactor.
• The fuel transfer and washing cells within which irradiated fuel sub-assemblies were processed and residual sodium
coolant removed.
• The fuel storage ponds.
Man access to several areas (particularly the waste vault) was not possible due to very high radiation levels from stored ??active
wastes or residual contamination and in these cases specially engineered remote camera and detector deployment systems
were developed and used. In other areas, such as the ponds, limited man access was possible under prepared and controlled conditions.
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Abstracts Session 56
2) HUMAN RELIABILITY-BASED MC&A MODELING FOR EVALUATING
THE EFFECTIVENESS OF PROTECTING NUCLEAR MATERIAL (wP-59379)
Felicia A Durán, Gregory D. Wyss, Sandia National Laboratories (USA)
Material control and accountability (MC&A) operations that track and account for critical assets at nuclear facilities provide a
key protection approach for defeating insider adversaries. MC&A activities, from monitoring to inventory measurements, provide
critical information about target materials and define security elements that are useful against insider threats. However, these activities
have been difficult to characterize in ways that are compatible with the path analysis methods that are used to systematically
evaluate the effectiveness of a sites protection system. The path analysis methodology focuses on a systematic, quantitative evaluation
of the physical protection component of the system for potential external threats, and often calculates the probability, P(E),
that the PPS is effective in defeating an adversary who uses that attack pathway. In previous work, Dawson and Hester observed
that many MC&A activities can be considered a type of sensor system with alarm and assessment capabilities that provide reoccurring
opportunities for detecting the status of critical items. This work has extended this characterization of MC&A activities as
probabilistic sensors that are interwoven within each protection layer of the PPS. In addition, MC&A activities have similar characteristics
to operator tasks performed in a nuclear power plant (NPP) in that the reliability of these activities depends significantly
on human performance. Many of the procedures involve human performance in checking for anomalous conditions. Further
characterization of MC&A activities as operational procedures that check the status of critical assets provides a basis for applying
human reliability analysis (HRA) models and methods to determine probabilities of detection for MC&A protection elements...
3) RISK-BASED SECURITY COST-BENEFIT ANALYSIS: METHOD AND EXAMPLE
APPLICATIONS (w/oP-59381)
Gregory Wyss, John Hinton, John Clem, Consuelo Silva, Felicia A Durán, Sandia National Laboratories (USA)
Decision makers wish to use risk-based cost-benefit analysis to prioritize security investments. However, understanding security
risk requires estimating the likelihood of attack, which is extremely uncertain and depends on unquantifiable psychological factors
like dissuasion and deterrence. In addition, the most common performance metric for physical security systems, probability
of effectiveness at the design basis threat [P(E)], performs poorly in cost-benefit analysis. It is extremely sensitive to small changes
in adversary characteristics when the threat is near a systems breaking point, but very insensitive to those changes under other conditions.
This makes it difficult to prioritize investment options on the basis of P(E), especially across multiple targets or facilities.
To overcome these obstacles, a Sandia National Laboratories Laboratory Directed Research and Development project has
developed a risk-based security cost-benefit analysis method. This approach characterizes targets by how difficult it would be for
adversaries to exploit each targets vulnerabilities to induce consequences. Adversaries generally have success criteria (e.g., adequate
or desired consequences and thresholds for likelihood of success), and choose among alternative strategies that meet these
criteria while considering their degree of difficulty in achieving their successful outcome. Investments reduce security risk as they
reduce the severity of consequences available and/or increase the difficulty for an adversary to successfully accomplish their most
advantageous attack...
SESSION 56 — ADVANCED L/ILW TECHNOLOGIES - PART 2 OF 2 (1.21)
1) APPLYING FLUID DYNAMICS SIMULATIONS TO IMPROVE PROCESSING AND
REMEDIATION OF NUCLEAR WASTE (wP-59172)
Kelly J Knight, Jon M. Berkoe, Brigette M. Rosendall, L. Joel Peltier, Chris A Kennedy, Bechtel National (USA)
Transport and processing of hazardous nuclear waste for treatment and storage can involve unique and complex thermal and
fluid dynamic conditions that pose potential for safety risk and/or design uncertainty and also are likely to be subjected to more
precise performance requirements than in other industries. From an engineering analysis perspective, certainty of outcome is essential.
Advanced robust methods for engineering analysis and simulation of critical processes can help reduce risk of design uncertainty
and help mitigate or reduce the amount of expensive full-scale demonstration testing.
This paper will discuss experience gained in applying computational fluid dynamics models to key processes for mixing, transporting,
and thermal treatment of nuclear waste as part of designing a massive vitrification process plant that will convert high and
low-level nuclear waste into glass for permanent storage. Examples from industrial scale simulations will be presented. The computational
models have shown promise in replicating several complex physical processes such as solid-liquid flows in suspension,
blending of slurries, and cooling of materials at extremely high temperature. Knowledge gained from applying simulation has provided
detailed insight into determining the most critical aspects of these complex processes that can ultimately be used to help guide
the optimum design of waste handling equipment based on credible calculations while ensuring risk of design uncertainty is minimized.
2) LIFETIME PERFORMANCE OF ASME AG-1 SECTION FK RADIAL FLOW FILTERS (wP-59170)
CHARLES WAGGONER, Michael Parsons, Paxton Giffen, Mississippi State University;
Jaime Rickert, Institute for Clean Energy Technology (USA)
A series of 18 filters Section FK filters have been tested. This included testing two different configurations of 2000 cfm filters,
12 remote change filters and 6 safe change filters. Testing consisted of lifetime performance evaluations using three different
aerosol challenges and two different relative humidity/temperature conditions. Challenge aerosols ranged in mass median diameter
(MMD) size from 500 nm (alumina) to 3000 nm (Arizona road dust). All testing was conducted consistent with NQA-1 standards.
Test data were continuously collected for volumetric airflow, air temperature, relative humidity, up and downstream particle
size distribution, up and downstream particle count, and filter differential pressure.
Data provided in this paper include the mass versus differential pressure (dP) loading curves demonstrating loading capacity
as a function of particle size. Results of mass loading are shown to follow current models for smaller aerosols, but large particle
challenges demonstrated higher loading capacities than expected. Data will also be provided to demonstrate changes in the filter
pack geometry during latter stages of loading (at differential pressures greater than 12-14 in. w.c. dP). This change in pleat geom-
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Session 57 Abstracts
etry (pleat collapse) leads to a threshold dP at which the differential pressure will continue to increase even if aerosols are no longer
added to the air flow. Data will be presented to demonstrate that reducing the airflow by 25 percent will counteract this runaway
increase in dP, even if reduction of airflow is done as late as 25+ in. w.c. Filter failure for the units tested ranged from 30 to 50 in.
wc...
3) ALTERNATIVE STRATEGIES TO REDUCE COST AND WASTE VOLUME IN
HEPA FILTRATION USING METALLIC FILTER MEDIA (wP-59348)
Chris Chadwick, Porvair Filtration Group (UK)
The disposal costs of contaminated HEPA and THE filter elements have been proved to be disproportionately high compared
with the cost of the elements themselves.
Work published elsewhere (Moore, et el 1992; Bergman et al 1997) suggests that the cost of use of traditional, panel type, glass
fibre HEPA filtration trains to the DOE was, during that period, $29.5million, based on a five year life cycle, and including installation,
testing, removal and disposal life cycle costs being based on estimates dating from 1987-1990.
Within that cost estimate, $300 was the value given to the filter and $4,450 was given to the peripheral activity. Clearly, if the
$4,450 component could be reduced, tremendous saving could ensue, in addition to the reduction of the legacy burden of waste volume.
This issue exists for operators in both the US and in Europe.
If HEPA filters could be cleaned to a condition where they could either be re-used or decontaminated to the extent that they
could be stored as a lower cost wasteform or if HEPA/THE filter elements were available without any organic content likely to give
rise to flammable or explosive decomposition gases during long term storage this would also reduce the costs and monitoring necessary
in storage.
4) ADVANCED DRYING SYSTEM TO MEET RADIOLYSIS CRITERIA OF METALLIC WASTE (wP-59116)
Masamichi Obata, Yasushi Ooishi, Toshiba Corporation (Japan)
High dose rate metal waste from core internals, such as BWR channel boxes or control rods are stored in fuel pool or site
bunker pool. Waste form for final disposal of these high dose rate metal wastes should eliminate water to prevent hydrogen gas
which can be caused by radiolysis of water. Toshiba’s newly developed drying system for high dose rate metal wastes enable very
low content of water even if the waste have a powder layer. Toshiba will provide the total system to fabricate the waste form for
high dose rate metal wastes.
SESSION 57 — RECENT ADVANCES IN PROCESSING AND IMMOBILIZATION
OF HLW, FISSILE AND TRU - PART 2 OF 2 (2.6)
1) MITIGATION OF SLIDING MOTION OF A CASK-CANISTER BY FLUID-STRUCTURE
INTERACTION IN AN ANNULAR REGION (wP-59208)
Tomohiro Ito, Atsuhiko Shintani, Chihiro Nakagawa, Osaka Prefecture University;
Kazuhisa Furuta, Osaka Prefcture University (Japan)
Many spent fuels coming out of the nuclear power station are planned to be stored in the special site in Japan until they are
reprocessed. In this site, the spent fuels are installed in a cylindrical container called canister. The canister, intern, will be installed
in the outer cylinder called cask that is a free-standing structure. When this system is subjected to the strong seismic motions, sliding
and rocking motions will be induced. And, in the worst case, the cask may collide to each other or overturn. Therefore, it is very
important to reduce these motions of the cask in order to avoid the consequent contamination of radioactive substances.
The authors have already conducted analytical investigations on the sliding and rocking motions of a cask-canister system subjected
to a seismic excitation, and clarified the effects of the vibration of the inner canister. It was shown that the inner canister
gives large influences on the sliding and rocking motions of the outer cask.
In this study, we propose a mitigation method for sliding motion. Water is installed in an annular region between a cask and a
canister. Fluid-structure interaction is taken into consideration for nonlinear sliding motion analyses. The effects of fluid-structure
interaction on mitigation of sliding motions are studied. Furthermore, these effects are confirmed experimentally using a fundamental
test model.
2) IODINE CONDITIONING AS IODATE ION IN AN APATITE-LIKE CERAMIC (w/oP-59015)
Lionel Campayo, CEA; Danielle Laurencin, Institut Charles Gerhardt De Montpellier;
Agnès Grandjean, Institut De Chimie Séparative De Marcoule; Remy Delorme, CEA (France)
Nuclear industry produces radionuclides like iodine-129 for which one of the management strategies could be an efficiently
conditioning over a geological time scale. Several materials have been proposed to meet this objective. One of the most promising
approaches consists in incorporating the element in robust inorganic matrices like apatites.
Apatites are a large family of compounds of general formula M10 (XO4 ) 6Y2 (M = Ca2+, Sr2+, Pb2+&; XO4 = (PO4 ) 3-, (VO4 ) 3- &; Y = OH-, F-&). Iodine has been incorporated in apatites under the form of iodide anions (I-), in compounds like
Pb10 (VO4 ) 4 . 8 (PO4 )1.2I2 which exhibits a good chemical resistance to the leaching by water. However, the number of apatite compositions
able to incorporate iodine as iodide is limited. Recently, we have started to develop a new way of incorporating iodine in
hydroxyapatite structures (M10 (PO4 ) 6 (OH) 2 , M = Ca or Sr) under mild conditions, using iodate anions (IO3 )-.
Here, the synthesis and characterization of these new iodate-substituted apatite phases will be presented. Their thermal stability
and their resistance to leaching will be described, revealing promising properties in view of radioactive iodine confinement
applications.
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Abstracts Session 57
3) STATUS OF THE DEVELOPMENT OF IN-TANK/AT-TANK SEPARATIONS TECHNOLOGIES
FOR HIGH-LEVEL WASTE PROCESSING FOR THE U.S. DEPARTMENT OF ENERGY (wP-59109)
Bill Wilmarth, SRNL; Nicholas P. Machara, US DOE Office of Technology Innovation and Deployment;
Steve P. Schneider, US DOE Office of Waste Processing; Reid A. Peterson, PNNL;
Sheryl R. Bush, SRNL (USA) Presentation by Jim Marra, US DOE (USA)
Within the U.S. Department of Energys (DOE) Office of Technology Innovation and Development, the Office of Waste Processing
manages a research and development program related to the treatment and disposition of radioactive waste. At the Savannah
River (South Carolina) and Hanford (Washington) Sites, approximately 90 million gallons of waste are distributed among 226
storage tanks (grouped or collocated in tank farms). This waste may be considered to contain mixed and stratified high activity and
low activity constituent waste liquids, salts and sludges that are collectively managed as high level waste (HLW). A large majority
of these wastes and associated facilities are unique to the DOE, meaning many of the programs to treat these materials are firstof-a-kind
and unprecedented in scope and complexity. As a result, the technologies required to disposition these wastes must be
developed from basic principles, or require significant re-engineering to adapt to DOEs specific applications. Of particular interest
recently, the development of In-tank or At-Tank separation processes have the potential to treat waste with high returns on financial
investment. The primary objective associated with In-Tank or At-Tank separation processes is to accelerate waste processing.
Insertion of the technologies will (1) maximize available tank space to efficiently support permanent waste disposition including
vitrification; (2) treat problematic waste prior to transfer to the primary processing facilities at either site (i.e., Hanfords Waste
Treatment and Immobilization Plant (WTP) or Savannah Rivers Salt Waste Processing Facility (SWPF)); and (3) create a parallel
treatment process to shorten the overall treatment duration...
4) THE DEVELOPMENT, TESTING AND DEMONSTRATION OF A NEW CLASS
OF INORGANIC ION SPECIFIC MEDIA EMPHASIZING THE OPTIMIZATION, STABILIZATION
AND VOLUME REDUCTION OF THE FINAL NUCLEAR WASTE FORM (w/oP-59126)
Mark Denton, Kurion Inc.; William D. Bostick, MCL, Inc. (USA)
The primary focus of this paper is on the development of two novel classes of Ion Specific Media (ISM). However, it is important
to note that these exclusively inorganic media were selectively designed to be compatible with advanced stabilization technologies
(e.g., solidification and vitrification) and act as the final, stabilized waste forms required for storage or disposal on site. The
purpose of developing such a class of high capacity and high specificity Ion Specific Media is to remove the recalcitrant isotopes
(e.g., Cs-137, Sr-90,Tc-99 and I 129) during supplemental treatment (including Pretreatment, Off-Spec Tanks and Secondary Waste
Treatment) and place them into very small packages for on-site storage, or HLW vitrification. These ISMs must also be a very stable
form themselves for such potentially long-term, in-tank or dry storage (i.e.,inorganic in nature, leach resistant, non-hydrogen
generating and amenable to future stabilization by thermal, or other, means).
Having completed testing on a full spectrum of ISMs with these qualifications and ones that will selectively handle the prominent
class drivers and recalcitrant isotopes in Commercial Nuclear Power Plants (NPPs) (e.g., Cs-137, Ni-63 and Sr-90), a further
down select was done at our licensed facility, Materials and Chemistry Laboratories (MCL), in Oak Ridge, Tennessee for DOE specific
isotope removal. This down select was carried out on batch reactors and columns at an analytical- and bench-scale on 1) near
neutral pH surrogates and actual feeds, 2) secondary waste stream, pH ~8-9 surrogates, 3) strontium (Sr 90) removal from chelated
tanks (weapons complex off-spec. tanks), and 4) high alkali tank Cs pretreatment, pH ~14. To further the efficacy testing here,
prior to on-site hot-cell testing at a government facility, testing was also successfully carried out on actual Commercial Nuclear
Power Plant waste streams, in both our Oak Ridge Lab as well as on site (including fuel pool and Boron Waste Storage Tank,
BWST) waste waters.
5) HIGH WASTE LOADING GLASS FORMULATIONS FOR HANFORD
HIGH-ALUMINUM HLW STREAMS (wP-59388)
Albert Kruger, US DOE (USA)
The current estimates and glass formulation efforts have been conservative in terms of achievable waste loadings. These formulations
have been specified to ensure that the glasses are homogenous, contain essentially no crystalline phases, are processable
in joule-heated, ceramic-lined melters and meet WTP Contract terms. The WTPs overall mission will require the immobilization
of tank waste compositions that are dominated by mixtures of aluminum (Al), chromium (Cr), bismuth (Bi), iron (Fe), phosphorous
(P), zirconium (Zr), and sulfur (S) compounds as waste-limiting components. Glass compositions for these waste mixtures
have been developed based upon previous experience and current glass property models. Recently, DOE has initiated a testing program
to develop and characterize HLW glasses with higher waste loadings. Results of this work have demonstrated the feasibility
of increases in waste loading from about 25 wt% to 33-50 wt% (based on oxide loading) in the glass depending on the waste stream.
It is expected that these higher waste loading glasses will reduce the HLW canister production requirement by about 25% or more.
Refractory components, such as crystalline alumina (corundum) or zirconia (baddeleyite) slow down the melting of glass
batches in continuous melters. This effect can be considerable. Gibbsite and boehmite are common minerals found in high-level
wastes.
6) THE DESIGN, DEVELOPMENT AND DEMONSTRATION OF A NEW MODULAR VITRIFICATION
SYSTEM (MVS®) FOR THE TREATMENT OF NUCLEAR WASTE (w/oP-59127)
Mark Denton, Gaetan Bonhomme, Kurion Inc. (USA)
The design and performance capabilities, of the Modular Vitrification System (MVS®), together with the latest results of
experimental tests, is herein described. The MVS® is a novel heat treatment system in which nuclear waste can be processed directly
inside the single-use, final disposal container. The MVS® single-use module consists of an outer canister, typically to be made
of stainless steel specified by the clients site and by the waste acceptance criteria of waste repositories, and an inner induction susceptor/crucible,
typically made out of graphite, which can be thermally insulated from the outer stainless canister. The inner crucible
is inductively heated to the appropriate temperature, from 800°C (low melting point glasses) to up to 1550°C, by an external
low frequency, alternating current (AC), water-cooled induction coil. The very wide range of operating temperatures, the independ-
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Session 58 Abstracts
ence of melter to the chemistry of the waste and glass (e.g., conductivity) and the fact that parts exposed to high temperature molten
glass are single-use, significantly decreases pre-treatment needs and permits making a wide range of vitrified products from borosilicate
glass to iron phosphate glass. Moreover, technology development cycles and deployment are much faster and less costly on a
single-use system designed to work for only a few hours at high temperatures in extreme conditions as compared to approximately
5 years for incumbent technologies.
SESSION 58 — D&D RADIOLOGICAL CHARACTERIZATION AND MONITORING (3.5)
1) QUANTIFYING TC-99 CONTAMINATION IN A FUEL FABRICATION PLANT (wP-59024)
Pete Burgess, Nuvia Ltd; Carol Darbyshire, Springfield Fuels Ltd (UK)
The need was to quantify contamination in a large redundant building at the Springfields fuel manufacturing facility. The aim
was to be able to identify any areas where the bulk activity exceeded 0.4 Bq/g Tc-99 as this would preclude the demolition rubble
being sent to the local disposal facility. The problems associated with this project were the presence of significant uranium contamination,
the realisation that both the Tc-99 and the uranium had diffused into the brickwork to a significant depth and the relatively
low beta energy of Tc-99. The uranium was accompanied by Pa-234m, an energetic beta emitter.
The first decision was to set up standard beta contamination monitors in an unusual way which minimised the response to other
nuclides present while leaving the response to Tc-99 unchanged. The response of the monitor was then determined for Tc-99 activity
buried at different depths. This could then be folded with any known concentration/depth profile to produce a response in
counts/s/Bq/g. The concentration/depth profile was determined for several areas on the plant for Tc-99 and for uranium. The radiochemical
analysis was performed locally but the performance of the local laboratory was checked during the initial investigation
by splitting samples three ways and having confirmation analyses performed by 2 other laboratories. The results showed surprisingly
consistent concentration gradients for Tc-99 and for uranium across the samples but the Tc-99 was clearly more “sticky” than
the uranium.
2) THE SCIENCE, ASSAYING AND WASTE SENTENCING OF ACTIVATED BIOSHIELDS (wP-59038)
Ian Adsley, Nuvia Limited (UK)
This paper describes the design and operation of the Combined Technology Automated Waste Characterisation System (CTA-
WCS) at JRC Ispra. The 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. The WCS covers a range of activity including
Low and Intermediate Level Waste (LLW and ILW). The 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.
The 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...
3) GAMMA-RAY IMAGING FOR GENERATING 3D DOSE RATE MAPS (wP-59123)
Karl Hughes, Edmund Cracknell, Babcock International Group (UK)
The use of gamma-ray imaging has become established in the nuclear industry, especially in the fields of decommissioning and
clean-up, for identifying the origins of elevated gamma dose rates. Since their first use in the mid 1990s, gamma-ray imaging
devices, such as the Babcock RadScan 800, have been used to produce colour overlay plots that indicate, in two dimensions, the
locations and distribution of radioactive contaminants. This information is invaluable in helping project managers to plan clean-up
and shielding activities, ensuring that all work carried out is cost effective and ALARP. Recent work undertaken by Babcock
demonstrates the capability to generate 3D maps of dose rate fields from the output of gamma-ray imaging work. The combination
of gamma-ray imaging survey and resultant dose map is a very powerful tool for planning decommissioning. The conventional
gamma-ray image provides an unambiguous identification of the origins of the dose rates present whilst the 3D dose map allows
the dose uptake to personnel to be determined. Furthermore, the ability to quantify the effect of clean-up or shielding on the dose
rates is possible, providing project teams with a metric for determining the best option available.
4) SAMPLING VS. TAKING SOME (wP-59349)
Dominique Francois-Bongarcon, AGORATEK International Consultants (Canada)
The problem of sampling in general, and for nuclear decontamination in particular, is properly defined. A theory is presented
(Gy’s Theory of Sampling, a.k.a. TOS) that brings all the answers and allows us to put them to work.
The author draws from his lifelong experience in research, teaching and practical applications in this domain to emphasize the
critical odds (i.e. risks) of not taking sampling explicitly into account when assessing grades and concentrations.
The evolution of the acceptance of this theory in the nuclear industry is finally illustrated, and a hopeful glimpse into the future
concludes the presentation.
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Abstracts Session 58
5) WASTE ASSESSMENT: A PRACTICAL APPROACH TO PROVING WASTE METALS SUITABLE
FOR CONSIGNMENT AS RADIOLOGICALLY EXEMPT MATERIALS (wP-59266)
Iain Carvel, RSRL; Richard D Gunn, Robin Strange, Christopher Orr, Babcock International Group (UK)
B220 at Harwell was built as a Radiochemical Research and Development facility in the latter part of the 1940s. The facility
has been operational since 1949 and has been extended several times, most notably the Plutonium Glove Box Wing in the 1950s
and the Remote Handling Wing in the 1980s. Only the Remote Handling wing remains operational, processing Historic Waste
which is being recovered from storage holes elsewhere on site. The remainder of the facility is undergoing progressive strip out and
decommissioning. In the Plutonium Wing and associated areas the waste fingerprint (nuclide vector) consists predominately of
alpha emitting radionuclides.
Decommissioning and Decontamination (D&D) operations often result in the production of large volumes of scrap metal waste
with little or no radioactive contamination. Proving that the waste is clean can be costly and time consuming, as the shape and size
of the metallic waste items often means that it is difficult or impossible to monitor all surfaces using conventional hand-held survey
meters. This is a particular problem for alpha contamination measurement.
Traditional radiological surveying techniques are very labour intensive and involve surveyors checking every surface using
hand held instruments and smear sampling the hard to access areas. Even then 100% monitoring cannot be guaranteed.
6) DEVELOPMENT OF A COMPUTER SYSTEM FOR SUPPORT AND DOCUMENTATION
OF CLEARANCE OF BUILDINGS OF NUCLEAR INSTALLATIONS (wP-59278)
Christoph Winkler, Stefan Woerlen, Stefan Thierfeldt, Frank Schartmann, Brenk Systemplanung (Germany)
Clearance of buildings of nuclear installations in Germany has to comply with general requirements laid down in Section 29
of the German Radiation Protection Ordinance (RPO; Strahlenschutzverordnung), clearance levels as stipulated in Table 1 of Annex
III RPO and technical guidance given in the technical standard DIN 25457. Clearance procedures are usually proposed by the
licensee and are made part of a decommissioning licence after appropriate review by the authorities. The clearance procedures consist
of a radiological characterisation of the various parts of the buildings, a decontamination step if necessary, followed by measurements
for checking the success of decontamination, and the actual decision measurements for demonstrating compliance with
clearance levels.
These three steps rely on various measurement methods, selected depending on the relevant radionuclides to be measured, like
sampling with subsequent gamma spectrometry (and if necessary separate evaluation of beta and alpha emitting nuclides), measurements
with surface contamination monitory and in situ gamma spectrometry. For a nuclear power plant, the number of samples
taken during this procedure can easily reach a few 10,000, while the number of single measurements can reach several 100,000 single
surface measurements and several 10,000 measurements with in situ gamma spectrometry. This large number of data together
with the correct interpretation according to the valid nuclide vector, the penetration depth of the contamination, the correction for
radioactive decay etc have to be managed, which is a error-prone process if carried out manually or with insufficient support by
customised software.
7) GEOSTATISTICAL METHODOLOGY FOR WASTE OPTIMIZATION
OF CONTAMINATED PREMISES (wP-59344)
Yvon Desnoyers, GEOVARIANCES; Didier Dubot, CEA/FAR/USLT/SPRE/SAS (France)
At the end of process equipment dismantling, the complete decontamination of nuclear facilities requires the radiological
assessment of residual activity levels of building structures. As stated by the IAEA: Segregation and characterization of contaminated
materials are the key elements of waste minimization.
From this point of view, the set up of an appropriate evaluation methodology is of prime importance. The radiological characterization
of contaminated premises can be divided into three steps. First, the most exhaustive facility analysis provides historical
and qualitative information. Then, a systematic (exhaustive or not) control of the radiation signal is performed by means of in situ
measurement methods such as surface control device combined with in situ gamma spectrometry. Besides, in order to assess the
contamination depth, samples can be collected at several locations within the premises and analysed. Combined with historical
information and radiation maps, such data improve and reinforce the preliminary waste zoning.
The relevance of the geostatistical methodology relies on the presence of a spatial continuity for radiological contamination.
In this case, geostatistics provides reliable methods for activity estimation, uncertainty quantification and risk analysis, which are
essential decision-making tools for decommissioning and dismantling projects of nuclear installations.
Besides, the geostatistical framework provides answers to several key issues that generally occur during the clean-up preparation
phase: How to optimise the investigation costs? How to deal with data quality issues? How to consistently take into account
auxiliary information such as historical inventory? How to integrate the remediation support into the modelling? How to quantify
uncertainties in the remediation costs while computing contaminated volumes?
8) DISCRIMINATION MONITORS FOR VARIOUS KINDS OF WASTE TO BE DOWN GRADED (wP-59117)
Susumu Naito, Syuji Yamamoto, Mikio Izumi, Masamichi Obata, Yukio Yoshimura,
Jiro Sakurai, Hitoshi Sakai, Toshiba Corporation (Japan)
During operation and maintenance, or decommissioning of nuclear power plant, various kind of waste should be treated, and
exposure control is also required. These wastes have a wide range of contamination, different composition of nuclides, and a different
shape, so each measurement instrument would be optimized for its use especially for very low level radioactivity measurement.
TOSHIBA provides appropriate equipment for any needs to discriminate the very low and non radioactive waste to save cost
of waste disposal, based on our original and innovative technology. For alpha emitting nuclides, we are ready to supply instruments
based on ionized particle measurement technology. For beta, gamma-emitting nuclides, we are ready to customize a shape of detector
based on our original plastic scintillation material. Some examples will be introduced.
129

Session 59 Abstracts
SESSION 59— RISK/PERFORMANCE ASSESSMENTS AND CONTAMINANT MIGRATION (4.7)
1) UNCERTAINTIES ON THE EXTENSION OF A POLLUTED ZONE (wP-59198)
Chantal de Fouquet, Mines ParisTech - Ecole des mines de Paris (France)
Data collected during the sampling of polluted sites are mainly used to characterize the concentration level and, through an
exploratory and variographic analysis, to characterize the spatial variability; at fixed support, to estimate the concentrations in order
to trace pollution map. In the case of kriging, this map is completed by the map of the standard deviation of the estimation error,
making it possible to delimit the zones in which the estimation is considered to lack in precision. If a proportional effect is present
(the local spatial variability depends on the local concentrations mean), the map of error standard deviation has to be corrected to
take into account the increase of spatial variability with the local concentration mean.
A confidence interval can be derived conventionaly from the kriging estimation and the associated error standard deviation.
For a fixed limit threshold, the polluted site can then be divided in three areas: the polluted zone, at a fixed statistical risk; the not
polluted zone, at a fixed statistical risk; the zone of uncertainty, in which the estimated concentrations are close to the threshold.
Because of the estimation error, it is not possible to specify if the exact concentrations exceed or not the threshold.
In the case of a soil pollution by hydrocarbons, usual and geostatistical forecasts are compared. The effective consequences of
these various forecasts on the quality of the site remediation are quantified and discussed.
2) IDENTIFICATION AND IMPLEMENTATION OF END-USER NEEDS DURING DEVELOPMENT
OF A STATE-OF-THE-ART MODELING TOOLSET (wP-59069)
Roger Seitz, SRNL; Mark Freshley, PNNL; Susan Hubbard, Lawrence Berkeley National Lab;
Mark Williamson, US DOE; Paul Dixon, LANL; Kurt Gerdes, DOE EM; Yvette Collazo , US DOE (USA)
The U.S. Department of Energy (USDOE) Office of Environmental Management, Technology Innovation and Development is
supporting development of the Advanced Simulation Capability for Environmental Management (ASCEM). ASCEM is an emerging
state-of-the-art scientific approach and software infrastructure for understanding and predicting contaminant fate and transport
in natural and engineered systems. The modular and open-source high performance computing tools will facilitate integrated
approaches that enable standardized assessments of performance and risk for EM cleanup and closure decisions.
Recognizing end-user needs and engaging end-users in the development process is expected to lead to better development and
implementation of the toolsets in the user community. End-user involvement in ASCEM covers a broad spectrum of perspectives,
including: performance assessment (PA) and risk assessment practitioners, research scientists, decision-makers, oversight personnel,
and regulators engaged in the USDOE cleanup mission. The intent is to facilitate regular feedback between the scientists and
modeling experts developing the tools and the practitioners and stakeholders in the field who will be implementing the tools for
decision-making.
End-users are engaged in ASCEM in three specific activities: User Steering Committee, user needs interface task, and demonstrations
of the ASCEM tools. The User Steering Committee comprises management from USDOE Field Offices, USDOE Contractors,
and regulatory bodies and is tasked with providing suggestions and feedback for the development team from a higher-level
implementation perspective. The user needs interface task is targeted at gathering and documenting suggestions and feedback from
practitioners and oversight personnel involved in day-to-day modeling, research and review activities at USDOE Sites. The demonstration
activities involve application of developing ASCEM tools and capabilities for representative problems at DOE sites.
3) URANIUM INVESTIGATION IN AN ALLUVIAL AQUIFER WITH DIRECT PUSH METHODS (w/oP-59281)
Fabian De Weirdt, Geoprobe Environmental Technologies s.a. (Belgium)
The U.S. EPA has established a maximum contaminant level of 30ug/l for uranium in drinking water due to its toxicity as a
heavy metal. This regulation has affected many small public water supply systems in the US and several of them are struggling to
come into compliance with the new standard. One such community is Clarks, NE, US which is situated on the alluvial deposits of
the Platte River that are underlain by the Cretaceous Age Niobrara formation. Geoprobe Systems coordinated with the Nebraska
Dept. of Health and Human Services, Water Well Stds. Program to investigate the cause of the elevated uranium in the groundwater
that supplies drinking water to the village of Clarks.
Initially hydraulic profiling tool (HPT) logs were obtained at selected locations across the Clarks well field. The HPT probe
was advanced to depths of almost 36m (120ft) at several locations and the logs provided detailed information about the hydrostratigraphy
of the local aquifer not available from the drillers logs. The HPT logs were used to guide selection of screen depths for
small diameter wells that were installed with direct push (DP) methods. A total of nine wells were installed at two locations at the
facility with well depths ranging from as little as 6m (20ft) to a maximum of 36m (118ft). All wells were grouted bottom-up with
a tremie tube using 25% solids bentonite slurry to assure screen interval isolation.
4) INDEPENDENT TECHNICAL REVIEWS FOR GROUNDWATER AND SOIL REMEDIATION
PROJECTS AT US DEPARTMENT OF ENERGY SITES (w/oP-59188)
Dawn Kaback, AMEC; Grover Chamberlain, DOE EM; John G. Morse, US DOE; Scott W. Petersen, CH2M Hill (USA)
The Department of Energy Office of Environmental Management has supported independent technical reviews of soil and
groundwater projects at multiple DOE sites over the last 10 years. These reviews have resulted in significant design improvements
to remedial plans that have accelerated cleanup and site closure. Many have also resulted in improved understanding of complex
subsurface conditions, promoting better approaches to design and implementation of new technologies.
Many of these reviews have been sponsored and coordinated through the Office of Technology Innovation and Development
(OTID), whose mission is to promote the practical application of innovative technologies and approaches. Reviews have also been
sponsored within the EM site cleanup program in concert with local regulators and stakeholders.
130

Abstracts Session 59
Independent technical reviews add value, because they provide another perspective to problem solving and act as a check for
especially challenging problems. By bringing in a team of independent experts with a broad experience base, alternative solutions
are recommended for consideration and evaluation. In addition, the independence of the panel can is significant, because it is able
to address politically sensitive issues. The expert panel members typically bring lessons learned from other sites to help solve problems
associated with their task at hand. However, their recommendations at a particular DOE site can often be applied at other DOE
sites, because of the common nature of many of the problems, making the review potentially even more valuable.
5) ADVANCED SIMULATION CAPABILITY FOR ENVIRONMENTAL MANAGEMENT (ASCEM) (wP-59065)
Paul Dixon, LANL; Mark Williamson, US DOE; Mark Freshley, Pacific Northwest National Lab;
David Moulton, LANL; Ian Gorton, Pacific Northwest National Laboratory; Elizabeth H. Keating, LANL;
Yvette Collazo , US DOE; Kurt Gerdes, DOE EM; Juan Meza, Lawrence Berkeley National Laboratory (USA)
The U.S. Department of Energy Office of Environmental Management, Technology Innovation and Development determined
that the uniform application advanced modeling in the subsurface could potentially reduce the cost and risk associated with their
environmental cleanup mission. In response to this determination, the EM office of Technology Innovation and Development,
Groundwater and Soil Remediation (EM-32) began the program Advanced Simulation Capability for Environmental Management
(ASCEM) in 2010. ASCEM is a state-of-the-art scientific tool and approach for understanding and predicting contaminant fate and
transport in natural and engineered systems. The modular and open source high performance computing tool will facilitate integrated
approaches to modeling and site characterization that enable robust and standardized assessments of performance and risk for
EM cleanup and closure activities.
The ASCEM initiative supports the reduction of uncertainties and risks associated with DOE-EMs environmental cleanup and
closure programs by better understanding and quantifying the subsurface flow and contaminant transport behavior in complex geological
systems. This includes the long-term performance of engineered components, including cementitious materials in nuclear
waste disposal facilities that may be sources for future contamination of the subsurface. This paper, at a high level, will describe
the ASCEM tools, approach, recent technical reports and programmatic accomplishments completed in 2010.
6) A PHYSIOCHEMICAL ANALYSIS OF THE MECHANISMS FOR TRANSPORT AND
RETENTION OF TECHNETIUM (TC-99) IN UNSATURATED SOILS (w/oP-59050)
Danielle P Jansik, Dawn Wellman, Elsa Cordova, DeNomy Dage, PNNL;
Dorthe Wildenschild, Oregon State University (USA)
The transport of technetium (Tc-99), is of interest due to the potential for human exposure and impact on ecosystems. Technetium
has been released to the environment through nuclear power production and nuclear fuel processing; as a result, further
spreading of Tc-99 is a concern at DOE sites across the US. Specifically, technetium is a contaminant of concern at the Hanford
Site in southeastern Washington, due to the magnitude of material that was disposed. The current body of work conducted on Tc-
99 has provided a wealth of information regarding the redox relationships, sorption, solubility, and stability of the mineral phases
(Artinger et al., 2003; Beals and Hayes, 1995; Cui and Eriksen, 1996b; Gu and Schulz, 1991; Jaisi et al., 2009; Keith-Roach et al.,
2003; Kumar et al., 2007), however little work has been conducted on the transport of technetium in unsaturated soils.
Current conceptual models do not explain the persistence and presence of technetium in deep vadose zone environments such
as the Hanford site. In an oxic reducing environment with low organic content the residence time of technetium is the soil would
be expected to be low, due to its low sorption and high solubility. Surprisingly, nearly 50 years following the release of contamination
into the site, much of the element has persisted in the subsurface. Using an integrated testing approach we examined the mechanisms
for physical and chemical retention and transport of technetium. By employing transport and breakthrough curve analysis
as well as pore water and sequential extractions, we evaluated transport behavior, technetium mineral association, and technetium
leachability with regard to pore size distribution.
7) INTERMEDIATE AND LONG-TERM RADIOLOGICAL CONSEQUENCES OF UNCONTROLLED
SALINE SOLUTION ACCESS INTO ASSE MINE (wP-59163)
Veronika Ustohalova, Christian Küppers, Öko-Institut e.V. (Germany)
The Asse salt mine was used as a test site for radioactive waste disposal in salt formations between 1967 and 1978. At that
time, low- and intermediate-level radioactive waste was placed in chambers at a depth of about 750 m and 511 m below ground.
Due to geological conditions and anthropogenic activities, the mine is instable such that water penetrates into it. The main cause of
the mines instabilities comes from a large volume of dead space in the form of drifts and chambers in the salt rock. This space is
close to the adjoining rock. As a consequence, clefts in surrounding rocks have developed. Since 1988, salt-saturated groundwater
has been leaking into the upper part of the southern flank of the mine. These instabilities create a high risk of mine collapse with
an uncontrolled inflow of brine. There-fore, a suitable decommissioning concept is currently in development.
Brine inflow is managed under solution management. Uncontrolled brine inflow, however, occurs when there is a higher inflow
of solution, that beyond the capability of solution management. In this case, radionuclides from radioactive wastes come into contact
with brine and are dissolved into the solution. If the mine collapses, the brine is pressed into groundwater. The radionuclides
could then migrate with groundwater into the biosphere and cause radioactive exposure.
8) COST BENEFIT ASSESSMENT ACCORDING TO FRENCH METHODOLOGY (w/oP-59310)
Philippe Pouget-Abadie, Pricop-Bass Tudor, URS (France)
The site has been operated since 1903 for various metallurgy-related activities, as well as foundry activities. It covers a total
surface area of 11 ha. Following the partial cessation of industrial activities, the sites western part (approximately 5 ha) was sold
to a developer for the creation of an artisanal, tertiary and industrial activity estate.
URS was jointly commissioned by the sites former operator and by the developer to perform complementary site characterisation
studies in order to assess the sites compatibility with the future site use as well as to assess the costs of potential remedial
works.
131

Session 60 Abstracts
A cost-benefit assessment was conducted by URS and focused on management of soils excavated in the context of the development
project. The solutions considered comprised:Disposal of excavated soils in Class II or Class I landfills. This solution is the
most systematic and therefore the fastest, which is an advantage in the context of the implementation of the development. However,
associated costs are estimated at 2.3 M¬ and will have to be managed based on unit prices. Reuse of excavated soils on site as
fill materials, combined with off-site disposal of excess non-reusable volumes. The projects grades were adjusted on this…
SESSION 60 — BEST POSTERS OF ICEM 2011
ABSTRACTS NOT REQUIRED
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132

ICEM'11 Pre-Registration Attendee List — By Last Name
(Listed are only confirmed paid registrants as of 9-5-2011)
A
Dzhamshed Abdushukurov S.U.UMAROV PHYSICAL -
TECHNICAL INSTITUTE OF
ACADEMY OF SCIENCES OF
REPUBLIC OF TAJIKISTAN
Tajikistan
Andris Abramenkovs LATVIAN ENVIRONMENT,
GEOLOGY AND
METEOROLOGY CENTRE
Latvia
William Abramson LAWRENCE LIVERMORE
NATIONAL LABORATORY
United States
Rateb (Boby) Abu-Eid U.S. NRC United States
Valerie Adsley GUEST United Kingdom
Ian Adsley NUVIA LTD United Kingdom
Joerg Aign WESTINGHOUSE ELECTRIC Germany
GERMANY GMBH
Fouad Al-Musawi IRAQ MINISTRY
OF SCIENCEAND
TECHNOLOGY
Iraq
Keith Anderson ECC United States
Johan Andersson JA STREAMFLOW AB Sweden
Thierry Andre ONET TECHNOLOGIES
GRANDS PROJETS
France
Andrea Antus PAKS NUCLEAR POWER
PLANT LTD
Hungary
Shiho Asai JAPAN ATOMIC ENERGY
AGENCY
Japan
Rosemarie Atabek CEA SACLAY France
Julien Attiogbe GEOVARIANCES France
Emilie Aubonnet GEOVARIANCES France
Annabelle Axinn
B
GUEST Unites States
Douglas Bablitch AMEC EARTH AND
INRASTRUCTURE
United States
Ian Bainbridge ATOMIC ENERGY OF
CANADA LIMITED
Canada
Andrew Baker EDEN NUCLEAR AND
ENVIRONMENT LTD.
United Kingdom
Jonathan Baker CH2M HILL United Kingdom
Francesco Basile EUROPEAN COMMISSION
- JRC ISPRA
Italy
Tamara Baldwin GALSON SCIENCES
LIMITED
United Kingdom
Gheorghe Barariu RAAN-SITON Romania
Yves Barré CEA France
Angela Bartlett RESEARCH SITES
RESTORATION LTD
United Kingdom
Olga Batyukhnova GUEST Ukraine
Ian Beadle AMEC United States
Christophe Behar CEA France
Stephane Belbeze ANTEA France
Gary Benda ICEM'11 CONFERENCE
MANAGER
United States
Dianne Benda ICEM'11 GUEST TOURS United States
Michel Berte AREVA France
Claude Besson CARBODIAM S.A. Belgium
Hervé Bienvenu ANDRA France
Christophe Binet AREVA France
Yvon Bladier CONSULTANT France
Ludovic Blanc SARP INDUSTRIES France
Tiffany Blanchard USDOE / NATIONAL
NUCLEAR
United States
James Blankenhorn PERMAFIX
ENVIRONMENTAL
SERVICES INC
United States
Mikhail Bogod JSC ECOMET-S Russia
Wilhelm Bollingerfehr DBE TECHNOLOGY GmbH Germany
Jean-Michel Boniface AREVA TA France
Robert Bonner URS United Kingdom
Peter Booth WSP E&E United Kingdom
Jorge Borque ENRESA Spain
Jean-Michel Bosgiraud ANDRA France
María Cecilia Bossio NUCLEAR REGULATORY
AUTHORITY
Argentina
Joseph Boucau WESTINGHOUSE ELECTRIC United States
COMPANY
Laurel Boucher THE LAUREL CO. United States
Bernard Boullis CEA-SACLAY France
Jos Boussu TECNUBEL Belgium
Shari Brabham CISS CORPORATION United States
Pam Bradford CISS CORPORATION Unites States
Marnix Braeckeveldt ONDRAF/NIRAS Belgium
Georg Braehler NUKEM TECHNOLOGIES
GMBH
Germany
Peter Brennecke CONSULTANT Germany
Daniel Brew ANSTO Australia
Kimberly Brewer ARS INTERNATIONAL, INC. Unites States
Steven Brown SENES CONSULTANTS LTD United States
Kathryn Brown GUEST United States
Jerome Brueziere AREVA NC France
Guy Brunel CEA France
Peter Burgess NUVIA LTD United Kingdom
Nazirzhon Buriev S.U.UMAROV PHYSICAL -
TECHNICAL INSTITUTE OF
ACADEMY OF SCIENCES OF
REPUBLIC OF TAJIKISTAN
Tajikistan
Klaus Büttner
C
NUKEM
TECHNOLOGIES GMBH
Germany
Maria Teresa Cafaggi GUEST Belgium
Bruno Cahen ANDRA France
Olivier Calixte ONET TECHNOLOGIES - France
ONECTRA France
Lionel Campayo CEA France
Dwight Campbell CONTAINER PRODUCTS
CORPORATION
Unites States
Jan Carlsson SKB Sweden
Andy Carr CALDER GROUP United Kingdom
Iain Carvel RESEARCH SITES
RESTOTATION LTD.
United Kingdom
Mike Cashin PORVAIR FILTRATION
GROUP LTD
United Kingdom
Jeremy Causse CEA France
Charlotte Cazala IRSN France
Didier Cerat CEA - CENTRE DE
MARCOULE
France
Michiel Ceulemans UMICORE Belgium
Jean-Michel Chabeuf AREVA France
Pascal Champ CEGELEC France
Neil Chapman ARIUS ASSOCIATES United States
Mrs. Chapman GUEST Unites States
Yih Ping Chen INSTITUTE OF NUCLEAR
ENERGY RESEARCH (INER)
Taiwan
Sylvain Chevassu ONET TECHNOLOGIES -
ONECTRA
France
Jean-Paul Chiles ECOLE DES MINES DE
PARIS
France
Apostolos Christodoulou VJ TECHNOLOGIES France
Robert Clark NUVIA LIMITED United Kingdom
Jane Clarke GUEST Canada
Gilles Clement AREVA BUVAL United States
Jean Pierre Cizel AREVA United States
John Cochran SANDIA NATIONAL
LABORATORIES
United States
Hans Codée COVRA N.V. Netherlands
Matthew Cole SA TECHNOLOGY United States
Danny Coleman ARS INTERNATIONAL, INC. Unites States
Yvette Collazo U.S. DEPARTMENT OF
ENERGY
Unites States
Judith Connell FLUOR United States
Carl Connell GUEST Unites States
Kevin Cook CERADYNE BORON
PRODUCTS
United States
133

134
ICEM'11 Pre-Registration Attendee List — By Last Name
(Listed are only confirmed paid registrants as of 9-5-2011)
Michael Cournoyer LOS ALAMOS NATIONAL
LABORATORY
United States
Jean-Marie Cuchet BELGONUCLEAIRE Belgium
Michael Cull TELEDYNE BROWN
ENGINEERING
United States
Dan Curry
D
URS United Kingdom
Erik Dagorn BUREAU VERITAS France
Vladimir Daniska DECOM, A.S. Slovak Republic
Didier Dall'ava CEA SACLAY France
Frederique Damerval AREVA France
Géraldine Dandrieux ASN France
Carol Darbyshire SPRINGFIELDS FUELS LTD United Kingdom
Mike Davies NUVIA LIMITED United Kingdom
Chantal De Fouquet ECOLE DES MINES DE
PARIS
France
Grégoire De Laval AREVA France
Pierre-Edouard
De La Ronciere
SPIE France
Patrick De Moura CEA France
Renate De Vos NUCLEAR RESEARCH
AND CONSULTANCY
GROUP
Netherlands
Fabian De Weirdt GEOPROBE
ENVIROMENTAL
TECHNOLOGIES S.A.
Belgium
Frank Deconinck CNE France
Ronald Dekker NRG Netherlands
Bernard Delannay CARBODIAM S.A. Belgium
Sylvie Delaplace SFEN France
Carole Delchet INSTITUT DE CHIMIE
SÉPARATIVE DE
MARCOULE, UMR 5257
France
Anne Delos AMPHOS 21
CONSULTING SL
France
Andrea Denby ATOMIC ENERGY OF
CANADA LIMITED
Canada
Mark Denton KURION, INC. United States
Debbie Denton GUEST Unites States
Yvon Desnoyers GEOVARIANCES France
Jas Devgun SARGENT & LUNDY United States
Michel Dilles AMTEK SAS Unites States
Vince Dilworth ASME United States
Nick DiMascio BARTLETT SERVICES INC. United States
Paul Dixon LOS ALAMOS NATIONAL
LABORATORY
United States
Mrs. Dixon Dixon GUEST Unites States
Ryosuke Doke JAPAN ATOMIC
ENERGY AGENCY
Japan
Emma Dorado Lopez ONDRAF/NIRAS Belgium
Philippe Doumerc AREVA NC France
Andrew Drom ENERGYSOLUTIONS
EU LTD
United States
James Droppo PACIFIC NORTHWEST
NATIONAL LABORATORY
United States
Tamar Droppo GUEST Unites States
Didier Dubot CEA France
Géraldine Dupuy DEWDROPS France
Felicia Durán SANDIA NATIONAL
LABORATORIES
United States
Anne Durand CEA CENTRE DE
MARCOULE
France
Michel Dutzer
E
ANDRA France
Takeshi Ebashi NUCLEAR WASTE
MANAGEMENT
ORGANIZATION OF
JAPAN (NUMO)
Japan
Andrew Edwards GUEST Unites States
Henrik Efraimsson SWEDISH RADIATION
SAFETY AUTHORITY
Sweden
Fredrik Ekenborg AB SVAFO Sweden
Enik Elter PAKS NUCLEAR
POWER PLANT LTD
Hungary
William Everett
F
DEWDROPS France
Sebastien Farin ANDRA France
Kapila Fernando AUSTRALIAN NUCLEAR
SCIENCE AND
TECHNOLOGY
ORGANISATION
Australia
Enoka Fernando GUEST Australia
Christopher Fisher OFFICE OF NUCLEAR
REGULATION
United Kingdom
Amelia Fogleman GUEST Unites States
Dyan Foss CH2M HILL PLATEAU
REMEDIATION COMPANY
United States
Adam Foster STUDSVIK, INC. United States
Angelika Fox CWN GRUPPE
BARSBÜTTEL
Germany
Dominique AGORATEK Canada
Francois-Bongarcon INTERNATIONAL
Laszlo Fritz
G
PUBLIC LIMITED
COMPANY FOR
RADIOACTIVE WASTE
MANAGEMENT (PURAM)
Hungary
Miklos Garamszeghy NWMO Canada
Ester García Tapias ENRESA Spain
Irina Gaus NAGRA Switzerland
Arnaud Gay AREVA France
Robert Geddes AMEC Canada
Alexander Gelbutovskiy JSC ECOMET-S Russia
Mark Gerchikov AMEC NSS Canada
Ludivine Gilli IRSN France
Emmanuel Girasa GDF SUEZ NUCLÉAIRE
FRANCE
France
Patrick Gobert WESTINGHOUSE
ELECTRIC COMPANY
United States
Rebecca Goddard GUEST Unites States
François-Michel Gonnot ANDRA France
Alexandre Gorbatchev COMMISSARIAT A
L'ENERGIE ATOMIQUE
ET AUX ENERGIES
ALTERNATIVES
France
Florence Goutelard CEA United States
Kapil Goyal LOS ALAMOS NATIONAL
LABORATORY
United States
Achla Goyal GUEST Unites States
Agnes Grandjean CEA France
Guy Granier CEA MARCOULE France
Dominique Grenêche SFEN France
Christian Gronemeyer GRS MBH Germany
Philippe Gros-Gean ONET TECHNOLOGIES France
Bertil Grundfelt KEMAKTA KONSULT AB Sweden
Philippe Guetat CEA France
Philippe Guiberteau
H
CEA SACLAY France
Steve Halliwell VJ TECHNOLOGIES, INC. United States
Matthieu Hallouin ANTEA GROUP France
Patricia Hamel-Bloch SFEN France
Eduard Hanslík T.G.MASARYK WATER
RESEARCH INSTITUTE
Czech Republic
Vaclav Hanusik VUJE, Inc. Slovak Republic
Tomoko Haraga JAPAN ATOMIC ENERGY
AGENCY
Japan
Frank Hardeman SCK-CEN Belgium
Susetyo Hario Putero GADJAH MADA
UNIVERSITY
Indonesia
Lee Hartley SERCO United Kingdom
Haruhi Hata JAPAN ATOMIC ENERGY
AGENCY
Japan
Markus Havertz FORSCHUNGZENTRUM
JÜLICH GMBH
Germany
Susan Hess AREVA United States
Alan Heyes KING'S COLLEGE, LONDON United Kingdom

ICEM'11 Pre-Registration Attendee List — By Last Name
(Listed are only confirmed paid registrants as of 9-5-2011)
Cathy Hickey CH2M HILL United States
Tim Hicks GALSON SCIENCES
LIMITED
United Kingdom
Günter Hillebrand NUCLEAR ENGINEERING
SEIBERSDORF GMBH
Austria
John Hollinden CONTAINER PRODUCTS
CORPORATION
Unites States
Dae-Seok Hong KAERI (KOREA ATOMIC
ENERGY RESEARCH
INSTITUTE)
Korea
Koch Horst RÖHR+STOLBERG GMBH Germany
Tomas Hrncir SLOVAK UNIVERSITY OF
TECHNOLOGY IN
BRATISLAVA
Slovak Republic
Karl Hughes BABCOCK
INTERNATIONAL
United Kingdom
Tim Hunter THE UNIVERSITY
OF LEEDS
United Kingdom
Arne Hüttmann
I
UMICORE Belgium
Atsushi Iizuka KOBE UNIVERSITY Japan
Nathalie Impens SCK-CEN Belgium
Tomoko Ishii RADIOACTIVE WASTE
MANAGEMENT FUNDING
AND RESEARCH CENTER
Japan
Tomohiro Ito OSAKA PREFECTURE
UNIVERSITY
Japan
Oleg Ivanov
J
NRC KURCHATOV
INSTITUTE
Russia
Albert Jacobs DEWDROPS France
Michael James SELLAFIELD LTD United Kingdom
David James DW JAMES
CONSULTING, LLC
United States
Juanita James GUEST Unites States
Steven Jameson STUDSVIK United States
Danielle Jansik PACIFIC NORTHWEST
NATIONAL LABORARY
United States
Michel Jeanjacques CEA/DEN/MAR/DPAD/CPRP France
Nicolas Jeannee GEOVARIANCES France
Chun-Ping Jen DEPT. MECHNICAL
ENGINEERING, NATIONAL
CHUNG CHENG
UNIVERSITY
Taiwan
Jongseon Jeon ENESYS CO., LTD. Korea
Bernard Jolly SFEN France
Angie Jones AMEC United States
Sammy Jones GUEST Unites States
Steven Joyce SERCO United Kingdom
Lawrence Judd NUVISION ENGINEERING United States
László Juhász NATIONAL RESEARCH
INSTITUTE FOR
RADIOBIOLOGY AND
RADIOHYGIENE
Hungary
Hagen Gunther Jung
K
NLWKN Germany
Dawn Kaback AMEC GEOMATRIX United States
Dennis Kelley PACIFI NUCLEAR
SOLUTIONS
United States
Terry Kelly PAR SYSTEMS LTD United Kingdom
Jeffrey Kerridge CH2M HILL United States
Ronald Keyser ORTEC United States
Merry Keyser GUEST Unites States
Kwang-Wook Kim KOREA ATOMIC ENERGY
RESEARCH INSTITUTE
Korea
Karen Kim ELECTRIC POWER
RESEARCH INSTITUTE
United States
Kazumi Kitayama NUCLEAR WASTE
MANAGEMENT
ORGANIZATION OF
JAPAN (NUMO)
Japan
Heather Klebba NFT United States
Thomas Kluth SIEMPELKAMP
NUK+LEARTECHNIK
GMBH
Germany
Kelly Knight BECHTEL NATIONAL, INC. United States
Ichizo Kobayashi KAJIMA CORPORATION Japan
Frank Köhler RÖHR + STOLBERG GMBH Germany
Ken Kok ASME United States
Ville Koskinen FORTUM Finland
Paul Kreitman WESTINGHOUSE
NUCLEAR SERVICES
United States
Heinz Kröger TÜV NORD ENSYS
HANNOVER GMBH
& CO. KG
Germany
Albert Kruger US DOE United States
Konstantin Kulikov NIPTB ONEGA OAO Russia
Takanori Kunimaru
L
JAEA Japan
Jean Paul Labeur AREVA - DAP France
Alastair Laird PROJECT TIME & COST United Kingdom
Tai-Wei Lan FUEL CYCLE AND
MATERIAL
ADMINISTRATION ATOMIC
ENERGY COUNCIL
Taiwan
Patrick Landais ANDRA France
Eric Lanes ANDRA France
Barbara Larsen GUEST Unites States
Toro Laszlo MATEFIN BUCURESTI Romania
Agnes Launay AREVA France
Gerard Laurent EDF/CIDEN United States
Marie Lavielle CEA France
Michèle Le Goff SFEN France
Arnaud Leclaire ANDRA France
Stephen Leclere SELLAFIELD LIMITED United Kingdom
John Lehew CH2M HILL PLATEAU
REMEDIATION COMPANY
United States
Alain Lemmens GDF SUEZ Belgium
Koen Lenie TECNUBEL Belgium
Célia Lepeytre CEA France
Bertrand Leterme SCK-CEN Belgium
Maria Lindberg STUDSVIK NUCLEAR AB Sweden
Pierre Lisbonne CEA France
Yung Liu ARGONNE NATIONAL
LABORATORY
United States
Jeffrey Lively
M
AMEC United States
Angela Mackintosh SELLAFIELD LIMITED United Kingdom
Juliann Maffett EDGEN MURRAY United States
Ryan Maitland OFFICE FOR NUCLEAR
REGULATION
United Kingdom
Tatiana Makarchuk JSC ATOMSTROYEXPORT Russia
Annafrancesca Mariani SOGIN S.P.A. Italy
Simon Martin SELLAFIELD LTD United Kingdom
Laurent Martinet AREVA NC France
John Mathieson NUCLEAR
DECOMMISSIONING
AUTHORITY
United Kingdom
Mrs. McCombie GUEST Switzerland
Charles McCombie ARIUS ASSOCIATION Switzerland
Keith McConnell U.S. NUCLEAR
REGULATORY
COMMISSION
United States
Jan Medved VUJE, INC. Slovak Republic
Afat Mehdiyeva NATIONAL AEROSPACE
AGENCY OF AZERBAIJAN
Azerbaijan Republic
Irena Mele IAEA Austria
Aurélie Merceille CEA MARCOULE France
Matthias Messer GNS Germany
Betty Meyer GUEST United States
Greg Meyer FLUOR GOVERNMENT
GROUP
United States
Arnaud Michelle SARP INDUSTRIES France
Maxime Michel-Noel ONET TECHNOLOGIES
- ONECTRA
France
Bill Miller AMEC United Kingdom
Ross Miller SANDIA NATIONAL
LABORATORIES
United States
135

136
ICEM'11 Pre-Registration Attendee List — By Last Name
(Listed are only confirmed paid registrants as of 9-5-2011)
Sergii Mitichkin CHERNOBYL NPP Ukraine
Motoyuki Mitsuda JAPAN ATOMIC
ENERGY AGENCY
Japan
Satoru Miyoshi OBAYASHI CORPORATION Japan
Fabrice Moggia AREVA France
Barry Moloney ENERGYSOLUTIONS United Kingdom
Jenny Morris GALSON SCIENCES
LIMITED
United Kingdom
Ronald Morris WESTINGHOUSE
ELECTRIC COMPANY
USA
United States
Mark Morton WORLEYPARSONS
POLESTAR
United States
Virginia Morton GUEST Unites States
Gary Mottershead VJ TECHNOLOGIES, INC. United States
Joachim Mueth PAUL SCHERRER INSTITUT Switzerland
Virgene Mulligan ARS INTERNATIONAL United States
Ronnie Mulligan GUEST Unites States
André Musolff BAM FEDERAL INSTITUTE Germany
FOR MATERIALS
RESEARCH AND TESTING
Tracy Mustin U.S. DEPARTMENT OF
ENERGY
Unites States
Gus Myers
N
BABCOCK SERVICES INC. United States
Jalal Naghiyev INSTITUTE OF RADIATION
PROBLEMS
Azerbaijan Republic
Takahiro Nakajima RWMC, JAPAN Japan
Garik Nalbandyan AREV SI CJSC Armenia
Vladimir Necas SLOVAK UNIVERSITY
OF TECHNOLOGY
Slovak Republic
Linde Nel NECSA South Africa
Thomas Nellemann DANISH
DECOMMISSIONING
Denmark
Tino Neumeyer BAM FEDERAL
INSTITUTE FOR
MATERIALS RESEARCH
AND TESTING
Germany
Mike Nichols PACTEC EPS LTD. Unites States
Massimiliano Nobile PROJECT
MANAGEMENT UNIT
Russia
Jean-Guy Nokhamzon CEA France
Christian Nowak CWN GRUPPE BARSBÜTTEL Germany
Bálint Nos PURAM Hungary
William Nutt
O
ARGONNE NATIONAL
LABORATORY
United States
Palut-Laurent Odile ASN France
Rachel O'donnell LLWR United Kingdom
Takao Ohi NUCLEAR WASTE
MANAGEMENT
ORGANIZATION OF
JAPAN (NUMO)
Japan
Michael Ojovan UNIVERSITY OF
SHEFFIELD
United Kingdom
Ralf Ohlhof TUEV NORD ENSYS
GMBH & CO
Germany
Keisuke Okumura JAPAN ATOMIC ENERGY
AGENCY (JAEA)
Japan
Donald Olson COLUMBIANA HI TECH United States
Frantisek Ondra DECOM, A.S. Slovak Republic
Hironori Onoe JAPAN ATOMIC
ENERGY AGENCY
Japan
Peter Ormai INTERNATIONAL
ATOMIC AGENCY (IAEA)
Austria
Gérald Ouzounian ANDRA France
Hitoshi Owada RADIOACTIVE WASTE
MANAGEMENT FUNDING
AND RESEARCH CENTER
Japan
Eliza Ozaine WESTINGHOUSE
ELECTRIC GERMANY
GMBH
Germany
P
Michal Panik SLOVAK UNIVERSITY
OF TECHNOLOGY IN
BRATISLAVA
Slovak Republic
Alexandros Papafotiou INTERA INC. SWISS
BRANCH
Switzerland
Martial Pardoen ELECTRABEL - GDF SUEZ Belgium
Alan Paulley QUINTESSA United Kingdom
Maiju Paunonen FORTUM POWER &
HEAT/ NUCLEAR WASTE
Finland
Stéphane Pepin FEDERAL AGENCY FOR
NUCLEAR CONTROL
Belgium
Jean-Jacques Peraudin GEOVARIANCES United States
Janez Perko BELGIAN NUCLEAR
RESEARCH CENTRE
SCK-CEN
Belgium
Geoffrey Peter OREGON INSTITUTE
OF TECHNOLOGY
PORTLAND CAMPUS
United States
Lucien Pillette-Cousin AREVA TA France
Patrick Pin AREVA NC France
Martin Plys FAUSKE &
ASSOCIATES, LLC
United States
Richard Poisson ANDRA France
Andreas Poller NAGRA, SWITZERLAND Switzerland
Edward Posivak WMG, INC. United States
Gilles Potier AREVA NC France
Calvert Pratt BABCOCK
NUCLEAR LIMITED
France
Jozef Pritrsky DECOM, A.S. Slovak Republic
John Proni FLORIDA
INTERNATIONAL
UNIVERSITY
United States
Maria Elena Proni
Q
GUEST Unites States
Thomas Quercetti BAM FEDERAL Germany
INSTITUTE FOR MATERIALS
RESEARCH AND TESTING
R
Krisztian Rado PUBLIC LIMITED COMPANY Hungary
FOR RADIOACTIVE
WASTE MANAGEMENT
(PURAM)
Rodolphe Raffard ANDRA France
Rosa Ramirez U.S. DEPARTMENT
OF ENERGY
United States
Rodrigo Raposo FEDERAL FLUMINENSE Brazil
De Almeida UNIVERSITY
John Raymont KURION, INC. United States
Marilyn Raymont GUEST Unites States
Reginald Recco AMETEK SAS Unites States
Philip Rendell NDA (RADIOACTIVE
WASTE MANAGEMENT
DIRECTORATE)
United Kingdom
Ian Richardson SELLAFIELD LIMITED United Kingdom
Steve Rima AMEC United States
Stéphanie Romero ALSTOM GRID France
Julie Rosello CEA CADARACHE France
Francesco Rossi EUROPEAN COMMISSION
- JRC ISPRA
Italy
David Rossiter LLW REPOSITORY LTD United Kingdom
Bernard Rottner ONET TECHNOLOGIES Unites States
Anne Marie Roux CEA France
Jean-Paul Roux GEOVARIANCES France
Joerg Rueedi NAGRA Switzerland
James Russell NEVADA NATIONAL
SECURITY SITE
United States
Woo-Seog Ryu
S
KAERI (KOREA ATOMIC
ENERGY RESEARCH
INSTITUTE)
Korea
Mike Sanchez PACTEC, INC. Unites States
Juan L. Santiago ENRESA Spain
Satoshi Sato INTERNATIONAL
ACCESS CORPORATION
Japan

ICEM'11 Pre-Registration Attendee List — By Last Name
(Listed are only confirmed paid registrants as of 9-5-2011)
Hisao Satoh MITSUBISHI MATERIALS
CORPORATION
Japan
Lutz Schneider STOLLER
INGENIEURTECHNIK GMBH
Germany
Jürg Schneider NAGRA, SWITZERLAND Switzerland
Richard Schwent GUEST Unites States
Daniela Seda GUEST Brazil
Kelly Sedor NUCLEAR WASTE
MANAGEMENT
ORGANIZATION
Canada
Sergey Semenov NATIONAL RESEARCH
CENTRE "KURCHATOV
INSTITUTE
Russia
Rainer Senger INTERA INC. SWISS
BRANCH
Switzerland
Emad Sharmsaldin IRAQ MINISTRY OF
SCIENCE AND
TECHNOLOGY
Iraq
John Shevelan LLWR LTD United Kingdom
Bill Shingler FLUOR GOVERNMENT
GROUP
United States
Peter Sibley ENERGYSOLUTIONS United Kingdom
Rolf Sjöblom TEKEDO AB Sweden
Alojz Slaninka VUJE, A.S. Slovak Republic
Ondrej Slávik VUJE, A.S. Slovak Republic
Joe Small UK NATIONAL
NUCLEAR LABORATORY
United Kingdom
Graham Smith GMS ABINGDON LTD United Kingdom
Jager Smith ENTERGY United States
Janet Smith GUEST Unites States
Malgorzata Sneve NRPA Norway
Marina Sokcic-Kostic NUKEM TECHNOLOGIES
GMBH
Germany
Stephanie Soton AREVA NC France
Thorsten Stahl GRS MBH Germany
Mathias Steinhoff ÖKO-INSTITUT Germany
Hans-Juergen Steinmetz FORSCHUNGSZENTRUM
JÜLICH GMBH
Germany
Vyacheslav Stepanov NRC KURCHATOV
INSTITUTE
Russia
Dmitry Stepennov NATIONAL RESEARCH
CENTRE "KURCHATOV
INSTITUTE"
Russia
Howard Stevens STUDSVIK, INC. United States
Dawn Stevens GUEST Unites States
Trevor Sumerling LLWR LTD United Kingdom
Karel Svoboda NUCLEAR RESEARCH
INSTITUTE REZ PLC.
Czech Republic
Milena Svoboda GUEST Czech Republic
Bryan Swinson PAJARITO SCIENTIFIC
CORPORATION
United States
Susan Sykes GUEST Canada
Jonathan Sykes
T
UNIVERSITY OF
WATERLOO
Canada
Ulrike Tack-Hillebrand GUEST Austria
Yusuke Takayama KOBE UNIVERSITY Japan
Stefan Thierfeldt BRENK
SYSTEMPLANUNG GMBH
Germany
Chauveau Thomas BOUYGUES
CONSTRUCTION
SERVICES NUCLEAIRES
France
Simon Thompson ENERGY SOLUTIONS United Kingdom
Patrice Torres ANDRA France
Yuki Tosaki GEOLOGICAL SURVEY
OF JAPAN, AIST
Japan
Pierre Trabuc CEA France
Ivo Tripputi SOGIN S.P.A. Italy
Peter Turza PUBLIC LIMITED
COMPANY FOR
RADIOACTIVE WASTE
MANAGEMENT (PURAM),
HUNGARY
Hungary
Chou Tzu-Hsing
U
INSTITUTE OF NUCLEAR
ENERGY RESEARCH
Taiwan
Daniele Ugolini CONSULTANT Italy
Ehrlicher Ulrich PAUL SCHERRER INSTITUT Switzerland
Veronika Ustohalova
V
OEKO-INSTITUT E.V. Germany
Walter Van Hecke AREVA France
Leo Van Velzen NUCLEAR RESEARCH &
CONSULTANCY GROUP
Netherlands
Rik Vanbrabant BELGOPROCESS Belgium
Tjalle Vandergraaf PROVIDENCE COLLEGE Canada
Evelyn Vandergraaf GUEST Canada
Serge Vanderperre TRACTEBEL ENGINEERING Belgium
Thierry Varet AREVA France
Tero Varjoranta INTERNATIONAL ATOMIC
ENERGY AGENCY (IAEA)
Austria
Claire-Emilie Vaudey AREVA France
Romain Vede AREVA France
Andreas Vesely NUCLEAR ENGINEERING
SEIBERSDORF
Austria
Jean-Marc Vidal COMMISSARIAT À
L'ENERGIE ATOMIQUE
France
Joerg Viermann GNS GESELLSCHAFT FUER Germany
NUKLEAR-SERVICE MBH
Bernard Vigreux SFEN France
Bernard Vignau
W
CEA SACLAY United States
Charles Waggoner INSTITUTE FOR CLEAN
ENERGY TECHNOLOGY
United States
André Wakker NRG Netherlands
Julie Ward ABORIGINAL AFFAIRS
AND NORTHERN
DEVELOPMENT
Canada
Michael Washer FOREIGN AFFAIRS
AND INTERNATIONAL
TRADE CANADA
Canada
Pippa Waterman ENERGYSOLUTIONS United Kingdom
Tsong-Yang Wei INSTITUTE OF NUCLEAR
ENERGY RESEARCH,
AEC, TAIWAN
Taiwan
Jeroen Welbergen COVRA N.V. United States
David Wells NUVIA LIMITED United Kingdom
Stephen Wickham GALSON SCIENCES LTD United Kingdom
Anders Wiebert SWEDISH RADIATION
SAFETY AUTHORITY Sweden
Craig Williamson SOUTH CAROLINA
RESEARCH AND
EDUCATION
FOUNDATION
United States
Bertrand Willmann AREVA United States
Keith Witwer IMPACT SERVICES, INC.,
GEOMELT DIVISION United States
Hui-Jun Won KAERI Korea
Christopher Woodhead
Y
SA ROBOTICS LTD United Kingdom
Shuichi Yamamoto OBAYASHI CORPORATION Japan
James Young
Z
UNIVERSITY OF LEEDS United Kingdom
Matej Zachar DECOM, A.S. Slovak Republic
André Zech SARP INDUSTRIES France
Robert L. Zelmer AECL - LLRWMO Canada
Donna Zelmer GUEST Canada
Franco Zorzoli CAMPOVERDE SRL Italy
Maria Zorzoli GUEST Italy
137

138
ICEM'11 Pre-Registration Attendee List — By Country
(Listed are only confirmed paid registrants as of 9-5-2011)
Armenia
Garik Nalbandyan AREV SI CJSC Armenia
Argentina
María Cecilia Bossio
Australia
NUCLEAR REGULATORY
AUTHORITY
Argentina
Daniel Brew ANSTO Australia
Kapila Fernando AUSTRALIAN NUCLEAR
SCIENCE AND
TECHNOLOGY
ORGANISATION
Australia
Enoka Fernando
Austria
GUEST Australia
Günter Hillebrand NUCLEAR ENGINEERING
SEIBERSDORF GMBH
Austria
Irena Mele IAEA Austria
Peter Ormai INTERNATIONAL ATOMIC
AGENCY (IAEA)
Austria
Ulrike Tack-Hillebrand GUEST Austria
Tero Varjoranta INTERNATIONAL ATOMIC
ENERGY AGENCY (IAEA)
Austria
Andreas Vesely
Azerbaijan Republic
NUCLEAR ENGINEERING
SEIBERSDORF
Austria
Afat Mehdiyeva NATIONAL AEROSPACE
AGENCY OF AZERBAIJAN
Azerbaijan Republic
Jalal Naghiyev
Belgium
INSTITUTE OF
RADIATION PROBLEMS
Azerbaijan Republic
Claude Besson CARBODIAM S.A. Belgium
Jos Boussu TECNUBEL Belgium
Marnix Braeckeveldt ONDRAF/NIRAS Belgium
Maria Teresa Cafaggi GUEST Belgium
Michiel Ceulemans UMICORE Belgium
Jean-Marie Cuchet BELGONUCLEAIRE Belgium
Fabian De Weirdt GEOPROBE
ENVIROMENTAL
TECHNOLOGIES S.A.
Belgium
Bernard Delannay CARBODIAM S.A. Belgium
Emma Dorado Lopez ONDRAF/NIRAS Belgium
Frank Hardeman SCK-CEN Belgium
Arne Hüttmann UMICORE Belgium
Nathalie Impens SCK-CEN Belgium
Alain Lemmens GDF SUEZ Belgium
Koen Lenie TECNUBEL Belgium
Bertrand Leterme SCK-CEN Belgium
Martial Pardoen ELECTRABEL - GDF SUEZ Belgium
Stéphane Pepin FEDERAL AGENCY FOR
NUCLEAR CONTROL
Belgium
Janez Perko BELGIAN NUCLEAR
RESEARCH CENTRE
SCK-CEN
Belgium
Rik Vanbrabant BELGOPROCESS Belgium
Serge Vanderperre
Brazil
TRACTEBEL ENGINEERING Belgium
Rodrigo Raposo FEDERAL FLUMINENSE Brazil
De Almeida UNIVERSITY
Daniela Seda
Canada
GUEST Brazil
Ian Bainbridge ATOMIC ENERGY OF
CANADA LIMITED
Canada
Jane Clarke GUEST Canada
Andrea Denby ATOMIC ENERGY OF
CANADA LIMITED
Canada
Dominique AGORATEK Canada
Francois-Bongarcon INTERNATIONAL
Miklos Garamszeghy NWMO Canada
Robert Geddes AMEC Canada
Mark Gerchikov AMEC NSS Canada
Kelly Sedor NUCLEAR WASTE
MANAGEMENT
ORGANIZATION
Canada
Susan Sykes GUEST Canada
Jonathan Sykes UNIVERSITY OF
WATERLOO
Canada
Tjalle Vandergraaf PROVIDENCE COLLEGE Canada
Evelyn Vandergraaf GUEST Canada
Julie Ward ABORIGINAL AFFAIRS
AND NORTHERN
DEVELOPMENT
Canada
Michael Washer FOREIGN AFFAIRS
AND INTERNATIONAL
TRADE CANADA
Canada
Robert L. Zelmer AECL - LLRWMO Canada
Donna Zelmer
Czech Republic
GUEST Canada
Eduard Hanslík T.G.MASARYK WATER
RESEARCH INSTITUTE
Czech Republic
Karel Svoboda NUCLEAR RESEARCH
INSTITUTE REZ PLC.
Czech Republic
Milena Svoboda
Denmark
GUEST Czech Republic
Thomas Nellemann
Finland
DANISH
DECOMMISSIONING
Denmark
Ville Koskinen FORTUM Finland
Maiju Paunonen
France
FORTUM POWER &
HEAT/ NUCLEAR WASTE
Finland
Thierry Andre ONET TECHNOLOGIES
GRANDS PROJETS
France
Rosemarie Atabek CEA SACLAY France
Julien Attiogbe GEOVARIANCES France
Emilie Aubonnet GEOVARIANCES France
Yves Barré CEA France
Christophe Behar CEA France
Stephane Belbeze ANTEA France
Michel Berte AREVA France
Hervé Bienvenu ANDRA France
Christophe Binet AREVA France
Yvon Bladier CONSULTANT France
Ludovic Blanc SARP INDUSTRIES France
Jean-Michel Boniface AREVA TA France
Jean-Michel Bosgiraud ANDRA France
Bernard Boullis CEA-SACLAY France
Jerome Brueziere AREVA NC France
Guy Brunel CEA France
Bruno Cahen ANDRA France
Olivier Calixte ONET TECHNOLOGIES -
ONECTRA
France
Lionel Campayo CEA France
Jeremy Causse CEA France
Charlotte Cazala IRSN France
Jean-Michel Chabeuf AREVA France
Pascal Champ CEGELEC France
Sylvain Chevassu ONET TECHNOLOGIES -
ONECTRA
France
Jean-Paul Chiles ECOLE DES MINES
DE PARIS
France
Apostolos Christodoulou VJ TECHNOLOGIES France
Didier Cerat CEA - CENTRE DE
MARCOULE
France
Erik Dagorn BUREAU VERITAS France
Didier Dall'ava CEA SACLAY France
Frederique Damerval AREVA France
Géraldine Dandrieux ASN France
Chantal De Fouquet ECOLE DES MINES
DE PARIS
France
Grégoire De Laval AREVA France
Pierre-Edouard
De La Ronciere
SPIE France
Patrick De Moura CEA France
Frank Deconinck CNE France
Sylvie Delaplace SFEN France
Carole Delchet INSTITUT DE CHIMIE
SÉPARATIVE DE
MARCOULE, UMR 5257
France

ICEM'11 Pre-Registration Attendee List — By Country
(Listed are only confirmed paid registrants as of 9-5-2011)
Anne Delos AMPHOS 21 France
CONSULTING SL
Yvon Desnoyers GEOVARIANCES France
Philippe Doumerc AREVA NC France
Didier Dubot CEA France
Géraldine Dupuy DEWDROPS France
Anne Durand CEA CENTRE DE France
MARCOULE
Michel Dutzer ANDRA France
William Everett DEWDROPS France
Sebastien Farin ANDRA France
Florence Gabillaud-Poillion ASN France
Arnaud Gay AREVA France
Ludivine Gilli IRSN France
Emmanuel Girasa GDF SUEZ France
NUCLÉAIRE FRANCE
François-Michel Gonnot ANDRA France
Alexandre Gorbatchev COMMISSARIAT A France
L'ENERGIE ATOMIQUE
ET AUX ENERGIES
ALTERNATIVES
Agnes Grandjean CEA France
Guy Granier CEA MARCOULE France
Dominique Grenêche SFEN France
Philippe Gros-Gean ONET TECHNOLOGIES France
Philippe Guetat CEA France
Philippe Guiberteau CEA SACLAY France
Matthieu Hallouin ANTEA GROUP France
Patricia Hamel-Bloch SFEN France
Albert Jacobs DEWDROPS France
Michel Jeanjacques CEA/DEN/MAR/DPAD/CPRP France
Nicolas Jeannee GEOVARIANCES France
Bernard Jolly SFEN France
Jean Paul Labeur AREVA - DAP France
Patrick Landais ANDRA France
Eric Lanes ANDRA France
Agnes Launay AREVA France
Marie Lavielle CEA France
Michèle Le Goff SFEN France
Arnaud Leclaire ANDRA France
Célia Lepeytre CEA France
Pierre Lisbonne CEA France
Laurent Martinet AREVA NC France
Aurélie Merceille CEA MARCOULE France
Arnaud Michelle SARP INDUSTRIES France
Maxime Michel-Noel ONET TECHNOLOGIES - France
ONECTRA
Fabrice Moggia AREVA France
Jean-Guy Nokhamzon CEA France
Palut-Laurent Odile ASN France
Gérald Ouzounian ANDRA France
Lucien Pillette-Cousin AREVA TA France
Patrick Pin AREVA NC France
Richard Poisson ANDRA France
Gilles Potier AREVA NC France
Calvert Pratt BABCOCK NUCLEAR France
LIMITED
Rodolphe Raffard ANDRA France
Stéphanie Romero ALSTOM GRID France
Julie Rosello CEA CADARACHE France
Anne Marie Roux CEA France
Jean-Paul Roux GEOVARIANCES France
Stephanie Soton AREVA NC France
Chauveau Thomas BOUYGUES France
CONSTRUCTION
SERVICES NUCLEAIRES
Patrice Torres ANDRA France
Pierre Trabuc CEA France
Walter Van Hecke AREVA France
Thierry Varet AREVA France
Claire-Emilie Vaudey AREVA France
Romain Vede AREVA France
Jean-Marc Vidal COMMISSARIAT À France
L'ENERGIE ATOMIQUE
Bernard Vigreux SFEN France
André Zech SARP INDUSTRIES France
Germany
Joerg Aign WESTINGHOUSE
ELECTRIC GERMANY
GMBH
Germany
Wilhelm Bollingerfehr DBE TECHNOLOGY GmbH Germany
Georg Braehler NUKEM TECHNOLOGIES
GMBH
Germany
Peter Brennecke CONSULTANT Germany
Klaus Büttner NUKEM TECHNOLOGIES
GMBH
Germany
Angelika Fox CWN GRUPPE
BARSBÜTTEL
Germany
Christian Gronemeyer GRS MBH Germany
Markus Havertz FORSCHUNGZENTRUM
JÜLICH GMBH
Germany
Koch Horst RÖHR+STOLBERG GMBH Germany
Hagen Gunther Jung NLWKN Germany
Thomas Kluth SIEMPELKAMP
NUK+LEARTECHNIK
GMBH
Germany
Frank Köhler RÖHR + STOLBERG GMBH Germany
Heinz Kröger TÜV NORD ENSYS
HANNOVER GMBH
& CO. KG
Germany
Matthias Messer GNS Germany
André Musolff BAM FEDERAL INSTITUTE Germany
FOR MATERIALS
RESEARCH AND TESTING
Tino Neumeyer BAM FEDERAL INSTITUTE Germany
FOR MATERIALS
RESEARCH AND TESTING
Christian Nowak CWN GRUPPE BARSBÜTTEL Germany
Ralf Ohlhof TUEV NORD ENSYS
GMBH & CO
Germany
Eliza Ozaine WESTINGHOUSE ELECTRIC Germany
GERMANY GMBH
Thomas Quercetti BAM FEDERAL INSTITUTE Germany
FOR MATERIALS
RESEARCH AND TESTING
Lutz Schneider STOLLER
INGENIEURTECHNIK
GMBH
Germany
Marina Sokcic-Kostic NUKEM
TECHNOLOGIES GMBH\
Germany
Thorsten Stahl GRS MBH Germany
Mathias Steinhoff ÖKO-INSTITUT Germany
Hans-Juergen Steinmetz FORSCHUNGSZENTRUM
JÜLICH GMBH
Germany
Stefan Thierfeldt BRENK
SYSTEMPLANUNG GMBH\
Germany
Veronika Ustohalova OEKO-INSTITUT E.V. Germany
Joerg Viermann
Hungary
GNS GESELLSCHAFT FUER Germany
NUKLEAR-SERVICE MBH\
Andrea Antus PAKS NUCLEAR POWER
PLANT LTD
Hungary
Enik Elter PAKS NUCLEAR POWER
PLANT LTD
Hungary
Laszlo Fritz PUBLIC LIMITED
COMPANY FOR
RADIOACTIVE WASTE
MANAGEMENT (PURAM)
Hungary
László Juhász NATIONAL RESEARCH
INSTITUTE FOR
RADIOBIOLOGY AND
RADIOHYGIENE\
Hungary
Bálint Nos PURAM Hungary
Krisztian Rado PUBLIC LIMITED
COMPANY FOR
RADIOACTIVE WASTE
MANAGEMENT (PURAM)
Hungary
Peter Turza
Indonesia
PUBLIC LIMITED
COMPANY FOR
RADIOACTIVE WASTE
MANAGEMENT (PURAM),
HUNGARY
Hungary
Susetyo Hario Putero GADJAH MADA
UNIVERSITY
Indonesia
139

140
ICEM'11 Pre-Registration Attendee List — By Country
(Listed are only confirmed paid registrants as of 9-5-2011)
Iraq
Fouad Al-Musawi IRAQ MINISTRY OF
SCIENCE AND
TECHNOLOGY
Iraq
Emad Sharmsaldin
Italy
IRAQ MINISTRY OF
SCIENCE AND
TECHNOLOGY
Iraq
Francesco Basile EUROPEAN COMMISSION
- JRC ISPRA
Italy
Annafrancesca Mariani SOGIN S.P.A. Italy
Francesco Rossi EUROPEAN COMMISSION
- JRC ISPRA
Italy
Ivo Tripputi SOGIN S.P.A. Italy
Daniele Ugolini CONSULTANT Italy
Franco Zorzoli CAMPOVERDE SRL Italy
Maria Zorzoli
Japan
GUEST Italy
Shiho Asai JAPAN ATOMIC
ENERGY AGENCY
Japan
Ryosuke Doke JAPAN ATOMIC
ENERGY AGENCY
Japan
Takeshi Ebashi NUCLEAR WASTE
MANAGEMENT
ORGANIZATION OF
JAPAN (NUMO)
Japan
Tomoko Haraga JAPAN ATOMIC
ENERGY AGENCY
Japan
Haruhi Hata JAPAN ATOMIC
ENERGY AGENCY
Japan
Atsushi Iizuka KOBE UNIVERSITY Japan
Tomoko Ishii RADIOACTIVE WASTE
MANAGEMENT FUNDING
AND RESEARCH CENTER
Japan
Tomohiro Ito OSAKA PREFECTURE
UNIVERSITY
Japan
Kazumi Kitayama NUCLEAR WASTE
MANAGEMENT
ORGANIZATION OF
JAPAN (NUMO)
Japan
Ichizo Kobayashi KAJIMA CORPORATION Japan
Takanori Kunimaru JAEA Japan
Motoyuki Mitsuda JAPAN ATOMIC
ENERGY AGENCY
Japan
Satoru Miyoshi OBAYASHI CORPORATION Japan
Takahiro Nakajima RWMC, JAPAN Japan
Takao Ohi NUCLEAR WASTE
MANAGEMENT
ORGANIZATION OF
JAPAN (NUMO)
Japan
Keisuke Okumura JAPAN ATOMIC
ENERGY AGENCY (JAEA)
Japan
Hironori Onoe JAPAN ATOMIC
ENERGY AGENCY (JAEA)
Japan
Hitoshi Owada RADIOACTIVE WASTE
MANAGEMENT FUNDING
AND RESEARCH CENTER
Japan
Satoshi Sato INTERNATIONAL ACCESS
CORPORATION
Japan
Hisao Satoh MITSUBISHI MATERIALS
CORPORATION
Japan
Yusuke Takayama KOBE UNIVERSITY Japan
Yuki Tosaki GEOLOGICAL SURVEY
OF JAPAN, AIST
Japan
Shuichi Yamamoto
Korea
OBAYASHI CORPORATION Japan
Dae-Seok Hong KAERI (KOREA ATOMIC
ENERGY RESEARCH
INSTITUTE)
Korea
Jongseon Jeon ENESYS CO., LTD. Korea
Kwang-Wook Kim KOREA ATOMIC ENERGY
RESEARCH INSTITUTE
Korea
Woo-Seog Ryu KAERI (KOREA ATOMIC
ENERGY RESEARCH
INSTITUTE)
Korea
Hui-Jun Won KAERI Korea
Latvia
Andris Abramenkovs
Netherlands
LATVIAN ENVIRONMENT,
GEOLOGY AND
METEOROLOGY CENTRE
Latvia
Hans Codée COVRA N.V. Netherlands
Renate De Vos NUCLEAR RESEARCH &
CONSULTANCY GROUP
Netherlands
Ronald Dekker NRG Netherlands
Leo Van Velzen NUCLEAR RESEARCH &
CONSULTANCY GROUP
Netherlands
André Wakker
Norway
NRG Netherlands
Malgorzata Sneve
Romania
NRPA Norway
Gheorghe Barariu RAAN-SITON Romania
Toro Laszlo
Russia
MATEFIN BUCURESTI Romania
Mikhail Bogod JSC ECOMET-S Russia
Alexander Gelbutovskiy JSC ECOMET-S Russia
Oleg Ivanov NRC KURCHATOV
INSTITUTE
Russia
Konstantin Kulikov NIPTB ONEGA OAO Russia
Massimiliano Nobile PROJECT MANAGEMENT
UNIT
Russia
Tatiana Makarchuk JSC ATOMSTROYEXPORT Russia
Sergey Semenov NATIONAL RESEARCH
CENTRE "KURCHATOV
INSTITUTE
Russia
Vyacheslav Stepanov NRC KURCHATOV
INSTITUTE
Russia
Dmitry Stepennov
Slovak Republic
NATIONAL RESEARCH
CENTRE "KURCHATOV
INSTITUTE"
Russia
Vladimir Daniska DECOM, A.S. Slovak Republic
Vaclav Hanusik VUJE, Inc. Slovak Republic
Tomas Hrncir SLOVAK UNIVERSITY
OF TECHNOLOGY IN
BRATISLAVA
Slovak Republic
Jan Medved VUJE, INC. Slovak Republic
Vladimir Necas SLOVAK UNIVERSITY
OF TECHNOLOGY
Slovak Republic
Frantisek Ondra DECOM, A.S. Slovak Republic
Michal Panik SLOVAK UNIVERSITY
OF TECHNOLOGY
IN BRATISLAVA
Slovak Republic
Jozef Pritrsky DECOM, A.S. Slovak Republic
Alojz Slaninka VUJE, A.S. Slovak Republic
Ondrej Slávik VUJE, A.S. Slovak Republic
Matej Zachar
South Africa
DECOM, A.S. Slovak Republic
Linde Nel
Spain
NECSA South Africa
Jorge Borque ENRESA Spain
Juan L. Santiago ENRESA Spain
Ester García Tapias
Sweden
ENRESA Spain
Johan Andersson JA STREAMFLOW AB Sweden
Jan Carlsson SKB Sweden
Fredrik Ekenborg AB SVAFO Sweden
Henrik Efraimsson SWEDISH RADIATION
SAFETY AUTHORITY
Sweden
Bertil Grundfelt KEMAKTA KONSULT AB Sweden
Maria Lindberg STUDSVIK NUCLEAR AB Sweden
Johanna Sandwall SWEDISH RADIATION
SAFETY AUTHORITY
Sweden
Rolf Sjöblom TEKEDO AB Sweden
Anders Wiebert SWEDISH RADIATION
SAFETY AUTHORITY
Sweden

ICEM'11 Pre-Registration Attendee List — By Country
(Listed are only confirmed paid registrants as of 9-5-2011)
Switzerland
Irina Gaus NAGRA Switzerland
Mrs. McCombie GUEST Switzerland
Charles McCombie ARIUS ASSOCIATION Switzerland
Joachim Mueth PAUL SCHERRER
INSTITUT
Switzerland
Alexandros Papafotiou INTERA INC.
SWISS BRANCH
Switzerland
Andreas Poller NAGRA, SWITZERLAND Switzerland
Joerg Rueedi NAGRA Switzerland
Jürg Schneider NAGRA, SWITZERLAND Switzerland
Rainer Senger INTERA INC. SWISS
BRANCH
Switzerland
Ehrlicher Ulrich
Taiwan
PAUL SCHERRER
INSTITUT
Switzerland
Yih Ping Chen INSTITUTE OF NUCLEAR
ENERGY RESEARCH (INER)
Taiwan
Chun-Ping Jen DEPT. MECHNICAL
ENGINEERING,
NATIONAL CHUNG
CHENG UNIVERSITY
Taiwan
Tai-Wei Lan FUEL CYCLE AND
MATERIAL
ADMINISTRATION ATOMIC
ENERGY COUNCIL
Taiwan
Chou Tzu-Hsing INSTITUTE OF NUCLEAR
ENERGY RESEARCH
Taiwan
Tsong-Yang Wei
Tajikistan
INSTITUTE OF NUCLEAR
ENERGY RESEARCH,
AEC, TAIWAN
Taiwan
Dzhamshed Abdushukurov S.U.UMAROV PHYSICAL -
TECHNICAL INSTITUTE
OF ACADEMY OF SCIENCES
Tajikistan
OF REPUBLIC OF TAJIKISTAN
Nazirzhon Buriev
Ukraine
S.U.UMAROV PHYSICAL -
TECHNICAL INSTITUTE
OF ACADEMY OF
SCIENCES OF REPUBLIC
OF TAJIKISTAN
Tajikistan
Olga Batyukhnova GUEST Ukraine
Sergii Mitichkin
United Kingdm
CHERNOBYL NPP Ukraine
Valerie Adsley GUEST United Kingdom
Ian Adsley NUVIA LTD United Kingdom
Andrew Baker EDEN NUCLEAR AND
ENVIRONMENT LTD.
United Kingdom
Jonathan Baker CH2M HILL United Kingdom
Tamara Baldwin GALSON SCIENCES
LIMITED
United Kingdom
Angela Bartlett RESEARCH SITES
RESTORATION LTD
United Kingdom
Robert Bonner URS United Kingdom
Peter Booth WSP E&E United Kingdom
Peter Burgess NUVIA LTD United Kingdom
Andy Carr CALDER GROUP United Kingdom
Iain Carvel RESEARCH SITES
RESTOTATION LTD.
United Kingdom
Mike Cashin PORVAIR FILTRATION
GROUP LTD
United Kingdom
Robert Clark NUVIA LIMITED United Kingdom
Dan Curry URS United Kingdom
Carol Darbyshire SPRINGFIELDS FUELS LTD United Kingdom
Mike Davies NUVIA LIMITED United Kingdom
Christopher Fisher OFFICE OF NUCLEAR
REGULATION
United Kingdom
Lee Hartley SERCO United Kingdom
Alan Heyes KING'S COLLEGE,
LONDON United Kingdom
Tim Hicks GALSON SCIENCES
LIMITED United Kingdom
Karl Hughes BABCOCK
INTERNATIONAL United Kingdom
Tim Hunter THE UNIVERSITY
OF LEEDS
United Kingdom
Michael James SELLAFIELD LTD United Kingdom
Steven Joyce SERCO United Kingdom
Terry Kelly PAR SYSTEMS LTD United Kingdom
Alastair Laird PROJECT TIME & COST United Kingdom
Stephen Leclere SELLAFIELD LIMITED United Kingdom
Angela Mackintosh SELLAFIELD LIMITED United Kingdom
Ryan Maitland OFFICE FOR NUCLEAR
REGULATION
United Kingdom
Simon Martin SELLAFIELD LTD United Kingdom
John Mathieson NUCLEAR
DECOMMISSIONING
AUTHORITY
United Kingdom
Bill Miller AMEC United Kingdom
Barry Moloney ENERGYSOLUTIONS United Kingdom
Jenny Morris GALSON SCIENCES
LIMITED
United Kingdom
Rachel O'donnell LLWR United Kingdom
Michael Ojovan UNIVERSITY OF
SHEFFIELD
United Kingdom
Alan Paulley QUINTESSA United Kingdom
Philip Rendell NDA (RADIOACTIVE
WASTE MANAGEMENT
DIRECTORATE)
United Kingdom
Ian Richardson SELLAFIELD LIMITED United Kingdom
David Rossiter LLW REPOSITORY LTD United Kingdom
John Shevelan LLWR LTD United Kingdom
Peter Sibley ENERGYSOLUTIONS United Kingdom
Joe Small UK NATIONAL NUCLEAR
LABORATORY
United Kingdom
Graham Smith GMS ABINGDON LTD United Kingdom
Trevor Sumerling LLWR LTD United Kingdom
Simon Thompson ENERGY SOLUTIONS United Kingdom
Pippa Waterman ENERGYSOLUTIONS United Kingdom
David Wells NUVIA LIMITED United Kingdom
Stephen Wickham GALSON SCIENCES LTD United Kingdom
Christopher Woodhead SA ROBOTICS LTD United Kingdom
James Young
United States
UNIVERSITY OF LEEDS United Kingdom
William Abramson LAWRENCE LIVERMORE
NATIONAL LABORATORY
United States
Keith Anderson ECC United States
Annabelle Axinn GUEST United States
Ian Beadle AMEC United States
Douglas Bablitch AMEC EARTH AND
INRASTRUCTURE
United States
Gary Benda ICEM'11 CONFERENCE
MANAGER
United States
Dianne Benda ICEM'11 GUEST TOURS United States
Tiffany Blanchard USDOE / NATIONAL
NUCLEAR
United States
James Blankenhorn PERMAFIX
ENVIRONMENTAL
SERVICES INC
United States
Joseph Boucau WESTINGHOUSE
ELECTRIC COMPANY
United States
Laurel Boucher THE LAUREL CO. United States
Shari Brabham CISS CORPORATION United States
Pam Bradford CISS CORPORATION United States
Kimberly Brewer ARS INTERNATIONAL, INC. United States
Steven Brown SENES
CONSULTANTS LTD
United States
Kathryn Brown GUEST United States
Dwight Campbell CONTAINER PRODUCTS
CORPORATION
United States
Mrs.Chapman GUEST United States
Neil Chapman ARIUS ASSOCIATES United States
Jean Pierre Cizel AREVA United States
Gilles Clement AREVA BUVAL United States
John Cochran SANDIA NATIONAL
LABORATORIES
United States
Matthew Cole SA TECHNOLOGY United States
Danny Coleman ARS INTERNATIONAL, INC. United States
141

142
ICEM'11 Pre-Registration Attendee List — By Country
(Listed are only confirmed paid registrants as of 9-5-2011)
Yvette Collazo U.S. DEPARTMENT United States
OF ENERGY
Carl Connell GUEST United States
Judith Connell FLUOR United States
Kevin Cook CERADYNE BORON United States
PRODUCTS
Michael Cournoyer LOS ALAMOS NATIONAL United States
LABORATORY
Michael Cull TELEDYNE BROWN United States
ENGINEERING
Mark Denton KURION, INC. United States
Jas Devgun SARGENT & LUNDY United States
Debbie Denton GUEST United States
Michel Dilles AMTEK SAS United States
Vince Dilworth ASME United States
Nick DiMascio BARTLETT SERVICES INC. United States
Paul Dixon LOS ALAMOS NATIONAL United States
LABORATORY
Mrs. Dixon Dixon GUEST Unites States
Andrew Drom ENERGYSOLUTIONS United States
EU LTD
James Droppo PACIFIC NORTHWEST United States
NATIONAL LABORATORY
Tamar Droppo GUEST United States
Felicia Durán SANDIA NATIONAL United States
LABORATORIES
Rateb (Boby) Abu-Eid U.S. NRC United States
Andrew Edwards GUEST United States
Amelia Fogleman GUEST United States
Dyan Foss CH2M HILL PLATEAU United States
REMEDIATION COMPANY
Adam Foster STUDSVIK, INC. United States
Patrick Gobert WESTINGHOUSE United States
ELECTRIC COMPANY
Rebecca Goddard GUEST United States
Florence Goutelard CEA United States
Achla Goyal GUEST United States
Kapil Goyal LOS ALAMOS NATIONAL United States
LABORATORY
Steve Halliwell VJ TECHNOLOGIES, INC. United States
Susan Hess AREVA United States
Cathy Hickey CH2M HILL United States
John Hollinden CONTAINER PRODUCTS United States
CORPORATION
David James DW JAMES United States
CONSULTING, LLC
Juanita James GUEST United States
Steven Jameson STUDSVIK United States
Danielle Jansik PACIFIC NORTHWEST United States
NATIONAL LABORARY
Angie Jones AMEC United States
Sammy Jones GUEST United States
Lawrence Judd NUVISION ENGINEERING United States
Dawn Kaback AMEC GEOMATRIX United States
Dennis Kelley PACIFI NUCLEAR United States
SOLUTIONS
Jeffrey Kerridge CH2M HILL United States
Merry Keyser GUEST United States
Ronald Keyser ORTEC United States
Karen Kim ELECTRIC POWER United States
RESEARCH INSTITUTE
Heather Klebba NFT United States
Kelly Knight BECHTEL NATIONAL, INC. United States
Ken Kok ASME United States
Paul Kreitman WESTINGHOUSE United States
NUCLEAR SERVICES
Albert Kruger US DOE United States
Barbara Larsen GUEST Unites States
Gerard Laurent EDF/CIDEN United States
John Lehew CH2M HILL PLATEAU United States
REMEDIATION COMPANY
Yung Liu ARGONNE NATIONAL United States
LABORATORY
Jeffrey Lively AMEC United States
Juliann Maffett EDGEN MURRAY United States
Keith McConnell U.S. NUCLEAR United States
REGULATORY
COMMISSION
Betty Meyer GUEST United States
Greg Meyer FLUOR GOVERNMENT United States
GROUP
Ross Miller SANDIA NATIONAL United States
LABORATORIES
Ronald Morris WESTINGHOUSE United States
ELECTRIC COMPANY USA
Mark Morton WORLEYPARSONS United States
POLESTAR
Virginia Morton GUEST United States
Gary Mottershead VJ TECHNOLOGIES, INC. United States
Ronnie Mulligan GUEST United States
Virgene Mulligan ARS INTERNATIONAL United States
Tracy Mustin U.S. DEPARTMENT United States
OF ENERGY
Gus Myers BABCOCK SERVICES INC. United States
Mike Nichols PACTEC EPS LTD. United States
William Nutt ARGONNE NATIONAL United States
LABORATORY
Donald Olson COLUMBIANA HI TECH United States
Jean-Jacques Peraudin GEOVARIANCES
Geoffrey Peter OREGON INSTITUTE OF United States
TECHNOLOGY
PORTLAND CAMPUS
Martin Plys FAUSKE & United States
ASSOCIATES, LLC
Edward Posivak WMG, INC. United States
John Proni FLORIDA United States
INTERNATIONAL
UNIVERSITY
Maria Elena Proni GUEST United States
Rosa Ramirez U.S. DEPARTMENT United States
OF ENERGY
John Raymont KURION, INC. United States
Marilyn Raymont GUEST United States
Reginald Recco AMETEK SAS United States
Steve Rima AMEC United States
Bernard Rottner ONET TECHNOLOGIES United States
James Russell NEVADA NATIONAL United States
SECURITY SITE
Mike Sanchez PACTEC, INC. United States
Richard Schwent GUEST United States
Bill Shingler FLUOR GOVERNMENT United States
GROUP
Jager Smith ENTERGY United States
Janet Smith GUEST United States
Dawn Stevens GUEST United States
Howard Stevens STUDSVIK, INC. United States
Bryan Swinson PAJARITO SCIENTIFIC United States
CORPORATION
Bernard Vignau CEA SACLAY United States
Charles Waggoner INSTITUTE FOR United States
CLEAN ENERGY
TECHNOLOGY
Jeroen Welbergen COVRA N.V. United States
Craig Williamson SOUTH CAROLINA United States
RESEARCH AND
EDUCATION FOUNDATION
Bertrand Willmann AREVA United States
Keith Witwer IMPACT SERVICES, INC., United States
GEOMELT DIVISION

Technical Program Organizers
TRACK CO-CHAIRS
TECHNICAL PROGRAM CO-CHAIRS
Gary Benda, Bartlett Services, Inc. (USA) and Dominique Grenêche, Consultant (FRANCE)
TRACK 1
Low/Intermediate-Level (L/ILW) Radioactive Waste Management
Angie Jones, AMEC (USA), Michel Dutzer, Andra (France), Jerome Brueziere, CEA (France), Marc Butez, CEA (France),
Christopher Joussot-Dubien, CEA (France)
TRACK 2
Spent Fuel, Fissile Material, Transuranic (TRU) and High-Level Radioactive Waste (HLW) Management
Heather Klebba, Nuclear Filter Technology (USA), Gerald Ouzounian, Andra (France)
TRACK 3
Facility Decontamination and Decommissioning (D&D)
Jas Devgun, Sargent & Lundy (USA), Jean-Guy Nokhamzon, CEA (France), Thierry Varet, AREVA – BU Value (France)
TRACK 4
Environmental Remediation (ER)
Steve Brown, Senes Consultants (USA), Didier Dubot, CEA (France), Sandrine Magdaliniuk, AREVA (France),
Jean-Guy Nokhamzon, CEA/DEN/DADN (France)
TRACK 5
Environmental Management (EM)/Public Involvement/Crosscutting Issues/Global Partnering
Judith (Judy) Connell, Fluor (USA), Regis Dalmas, EDF (France), Yvette Collazo, US DOE (USA)
Ana Han, US DOE (USA), Jim Marra, US DOE (USA), Gerald Ouzounian, Andra (France),
Jean-Guy Nokhamzon, CEA/DEN/DADN (France)
Session Organizers
Keith Anderson, ECC (USA)
Johan Andersson, JA Streamflow AB (Sweden)
Andrew Baker, Eden Nuclear and Environment Ltd. (UK)
Ian Beadle, AMEC (UK)
Gary Benda, Bartlett Services (USA)
Ed Bentz, EJ Bentz & Associates (USA)
Paul Black, Neptune and Company Inc (USA)
James Blankenhorn, Perma-Fix (USA)
Steve Brown, SENES Consultants Ltd (USA)
Jerome Brueziere, AREVA (France)
Sean Bushart, Electric Power Research Institute (USA)
Jean Paul Chiles, Ecole Mines (France)
Hans Codee, Corva (Netherlands)
Judith (Judy) Connell, Fluor (USA)
Yvette Collazo, US DOE (USA)
Ian Crossland, Crossland Consulting (UK)
Jean-Marie Cuchet, BELGONUCLEAIRE (Belgium)
Michael Cull, Teledyne (USA)
Didier Delmont, CEA (France)
Mark Denton, Kurion Inc. (USA)
Jas Devgun, Sargent & Lundy(USA)
Didier Dubot, CEA/FAR/USLT/SPRE/SAS (France)
Michel Dutzer, Andra (France)
Kapila Fernando, ANSTO (Australia)
Dominique Francois-Bongarcon, AGORATEK
International Consultants (Canada)
Mike Garamszeghy, Nuclear Waste Management
Organization (Canada)
Irina Gaus, Nagra (Switzerland)
Dominique Greneche, Consultant (France)
Mark Gerchikov, AMEC (Canada)
Donald Goebel, SEC (USA)
Jeffrey Griffin, SRNL (USA)
Ana Han, US DOE (USA)
Paul Haigh, The Paul Haigh Partnership (UK)
Cathy Hickey, CH2M Hill (USA)
Jean-Michel Hoorelbeke, ANDRA (France)
Natraj Iyer, SRNL (USA)
Angie Jones, AMEC (USA)
Heather Klebba, NFT (USA)
Ronald Keyser, ORTEC - AMETEK (USA)
John Mathieson, NDA (UK)
Vicki Maranville, AMEC (UK)
Jim Marra, US DOE (USA)
Adrian Mendez-Torres, SRNL (USA)
Bill Miller, AMEC (UK)
Horst Monken Fernandes, IAEA (Austria)
Jean-Guy Nokhamzon, CEA/DEN/DADN (France)
Karan North, Magnox Ltd (UK)
Michael Ojovan, University of Sheffield (UK)
Peter Ormai, IAEA (Austria)
Gerald Ouzounian, Andra (France)
Corhyn Parr, Nuclear Enterprises (UK)
Kanwar Raj, Bhabha Atomic Research Center (India)
Philip Rendell, NDA (UK)
Hans Riotte, OECD/NEA (France)
Roger Seitz, SRNL (USA)
Andy Szilagyi, US DOE (USA)
Anibal Taboas, Consultant (USA)
Patricia Torres, ANDRA (France)
Walter Van Hecke, AREVA (France)
Leo Van Velzen, NRG (Netherlands)
Thierry Varet, AREVA (France)
Bill Wilmarth, SRNL (USA)
David Wallace, CDM (USA)
Susan Walter, AECOM (USA)
Stephen Wickham, Galson Sciences Limited (UK)
Robert Zelmer, Atomic Energy of Canada Limited (Canada)
143

144
Conference Steering Committee
General Co-Chairs
Anibal Taboas, Consultant
Dominique Grenêche, Consultant
Conference Manager
Gary Benda, Bartlett Services
ICEM Project Director
Vince Dilworth, ASME
European Event Manager
Bernard Jolly, French Nuclear Energy Society (SFEN)
Technical Paper Submission; Abstracts, Bio's, Copyright, Drafts and/or Final Papers
Stacey Cooper, ASME
Shari Brabham, CISS Corporation
US Program Coordinator for the Technical Program, Non-Eu Conference Registration or Non-European
Union Vendor Exhibition
Shari Brabham, CISS Corporation
EU Coordinator for Reims, France and Other Local Aspects, Conference Facilities, Social Programs, Vendor
Arrangements, European Union (EU) Vendor Exhibition or EU Conference Registrations
Sylvie Delaplace, French Nuclear Energy Society (SFEN)
Technical Tours
Sylvie Delaplace, French Nuclear Energy Society (SFEN)
US Federal Liaison(s)
Yvette Collazo, US Department of Energy
Larry Camper US Nuclear Regulatory Commission
EU Liaison(s)
Bernard Jolly, French Nuclear Energy Society (SFEN)
IAEA Liaison
Irena Mele, IAEA, Division of Nuclear Fuel Cycle and Waste Technology
ASME ICEM'11 Conference Committee Liaisons
Vincent Dilworth, ASME
Anibal Taboas, Consultant, Environmental Engineering Division
Ken Kok, Consultant, Nuclear Engineering Division
French Nuclear Energy Society (SFEN)
Bernard Jolly, French Nuclear Energy Society (SFEN)

Schedule of Events
— SUNDAY, SEPTEMBER 25, 2011 —
Event Time Location
Golf Tournament 7:30am - 3:00pm Le Golf de Reims Champagne
Technical Training Course 9:00am - 4:00pm RCC - Room 5, 2nd Floor
Exhibitor Set Up 2:00pm - 8:00pm RCC - Exhibition Hall, 1st Floor
Registration 4:00pm - 7:00pm RCC - Foyer, 1st Floor
Author/Panelist/Co-Chair Check-in 4:00pm - 7:00pm RCC - Foyer, 1st Floor
Speakers Ready Area 4.00pm - 7:00pm RCC - Salle De Presse, 2nd Floor
Welcome Reception 6:00pm - 8:00pm RCC - “Le Bouchon” Space, 2nd Floor
— MONDAY, SEPTEMBER 26, 2011 —
Event Time Location
Registration 7:15am - 6:00pm RCC - Foyer, 1st Floor
Author/Panelist/Co-Chair Check-in 7:15am - 6:00pm RCC - Foyer, 1st Floor
Speakers Ready Area 7:15am - 5:00pm RCC - Salle De Presse, 2nd Floor
Speakers Briefing 7:30am - 8:00am RCC - “Le Millesime” Space, 1st Floor
Guest Welcome Reception 8.00am - 9:00am RCC - Room 1, 2nd Floor
Coffee Service - Pre Opening Session 8:00am - 9:00am RCC - “Le Bouchon” Space, 2nd Floor
Exhibitor Set up 8:00am - 11:00am RCC - Exhibition Hall, 1st Floor
Monday Morning Opening Session 9:00am - 12:30pm RCC - Salle Royale, 2nd Floor
Coffee Break After 3rd Speaker RCC - “Le Bouchon” Space, 2nd Floor
Poster Session 9 12:00pm - 5:45pm RCC - Exhibition Hall, 1st Floor
Exhibition Open 12:00pm - 6:00pm RCC - Exhibition Hall, 1st Floor
Lunch Break 12:30pm - 1:40pm RCC - Exhibition Hall, 1st Floor
Sessions 2 - 8 1:45pm - 6:00pm RCC - Rooms 1 - 10, 2nd Floor
Coffee Break 3:30pm - 4:10pm RCC - Exhibition Hall, 1st Floor
— TUESDAY, SEPTEMBER 27, 2011 —
Event Time Location
Speakers Ready Area 7:15am - 5:00pm RCC - Salle De Presse, 2nd Floor
Registration 7:15am - 6:00pm RCC - Foyer, 1st Floor
Author/Panelist/Co-Chair Check-in 7:15am - 6:00pm RCC - Foyer, 1st Floor
Speakers Briefing 7:30am - 8:00am RCC - “Le Millesime” Space, 1st Floor
Exhibit Hall Hours 8:30am - 8:00pm RCC - Exhibition Hall, 1st Floor
Sessions 10 - 18 8:30am - 12:30pm RCC - Rooms 1 - 10, 2nd Floor
Poster Session 19 8:30am - 5:45pm RCC - Exhibition Hall, 1st Floor
Coffee Break 10:15am - 10:40am RCC - Exhibition Hall, 1st Floor
Lunch Break 12:30pm - 1:40pm RCC - Exhibition Hall, 1st Floor
Sessions 20 - 28 1:45pm - 6:00pm RCC - Rooms 1 - 10, 2nd Floor
Coffee Break 3:30pm - 4:10pm RCC - Exhibition Hall, 1st Floor
Tuesday Exhibit Reception 6:00pm - 8:00pm RCC - Exhibition Hall, 1st Floor
— WEDNESDAY, SEPTEMBER 28, 2011 —
Event Time Location
Speakers Ready Area 7:15am - 5:00pm RCC - Salle De Presse, 2nd Floor
Registration 7:15am - 6:00pm RCC - Foyer, 1st Floor
Author/Panelist/Co-Chair Check-in 7:15am - 6:00pm RCC - Foyer, 1st Floor
Speakers Briefing 7:30am - 8:00am RCC - “Le Millesime” Space, 1st Floor
Sessions 29- 38 8:30am - 12:30pm RCC - Rooms 1 - 10, 2nd Floor
Exhibit Hall Hours 8:30am - 5:00pm RCC - Exhibition Hall, 1st Floor
Poster Session 39 8:30am - 5:45pm RCC - Exhibition Hall, 1st Floor
Coffee Break 10:15am - 10:40am RCC - Exhibition Hall, 1st Floor
Lunch Break 12:30pm - 1:40pm RCC - Exhibition Hall, 1st Floor
Sessions 40 – 49 1:45pm - 6:00pm RCC - Rooms 1 - 10, 2nd Floor
Coffee Break 3:30pm - 4:10pm RCC - Exhibition Hall, 1st Floor
Wednesday Banquet 7:30pm - 11:30 pm Champagne De Castelnau Caveau
— THURSDAY, SEPTEMBER 29, 2011 —
Event Time Location
Registration 7:15am - 12:30pm RCC - Foyer, 1st Floor
Speakers Ready Area 7:15am - 12:30pm RCC - Salle De Presse, 2nd Floor
Author/Panelist/Co-Chair Check-in 7:15am - 1:00pm RCC - Foyer, 1st Floor
Speakers Briefing 7:30am - 8:00am RCC - “Le Millesime” Space, 1st Floor
Exhibit Hall Hours 8:30am - 11:00am RCC - Exhibition Hall, 1st Floor
Poster Session 60 8:30am - 11:00am RCC - Exhibition Hall, 1st Floor
Sessions 50 – 59 8:30am - 12:30pm RCC – Rooms 1 - 10, 2nd Floor
Coffee Break 10:15am - 10:40am RCC - Exhibition Hall, 1st Floor
Conference Ends 12:30pm RCC - 1st Floor
— FRIDAY, SEPTEMBER 30, 2011 —
Event Time Location
Technical Tours Departure 7:00am Departs RCC