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

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