The 13th International Conference on Environmental ... - Events

Abstracts
and its power was 100 kWt at its construction and it was up-graded to 250 kWt by KAERI. <strong>The</strong> second reactor, KRR-2,
was a TRIGA MARK-III type with an open pool and a movable core and its power was 2 MWt. Its first criticality was
reached in 1972 and it had been operated for 55,000 hours till the decision to shut it down in 1995. In 1996, it was
concluded that KRR-1 and KRR-2 would be dismantled. A project was launched for the decommissioning of these
reactors in January 1997 with the goal of a completion by 2008. <strong>The</strong> total budget for the project is 20.0 million US
dollars, including the cost for the waste disposal and for the development of the technologies. <strong>The</strong> work scopes during the
reactor decommissioning project are the dismantling of all the facilities and the removal of all the radioactive materials
from the reactor site. After confirming the removal of the entire radioactivity by the MARSSIM concept, the site and
buildings will be released for an unrestricted use after the approval of the regulatory body. This paper summarizes on the
time tables, technologies, waste generation and treatment, manpower consumption, cost and radiation of work force and
analyzes the performance on the base of the original plan.
2) 40075 – Methods of Selected Input Calculation Data Verification And <strong>The</strong>ir Influence On Decommissioning
Cost In the OMEGA Code
Frantisek Ondra. Vladimir Daniska, Ivan Rehak, Oto Schultz, DECONTA, a.s. (Slovakia);
Vladimir Necas, Slovak University of Technology in Bratislava (Slovakia)
<strong>The</strong> aim of this contribution is development of methodology for verification of selected input calculation data
(performance unit parameters, work group structure, and duration of time-dependent activities) of the OMEGA Code in
the individual PSL (Proposed Standardised List) structure parts. <strong>The</strong> OMEGA Code, developed by DECOM, a.s., is used
for calculation of nuclear power plant decommissioning parameters and decommissioning planning. <strong>The</strong> code represents
a complex tool modelling a real flow of materials and radioactivity in the whole process of decommissioning, beginning
from pre-dismantling decontamination and terminating with either final disposal of radioactive waste or release of
non-contaminated materials to the environment. <strong>The</strong> analytical methodology for evaluation of input data inaccuracy
impacting on calculation of cost and other output decommissioning parameters was developed. This methodology is
based on application of coefficients representing calculated cost relative change for contingency adjustment purpose. <strong>The</strong>
decommissioning process includes significant amount of various technical as well s administrative activities.
Decommissioning parameters calculation is performed by calculation procedures modelling these decommissioning
activities. <strong>The</strong> procedures use for calculation a lot of input and unit data. Decommissioning calculation parameters
projects having been performed using the OMEGA Code showed the necessity of development of a new verification
module. This module is able to display selected input data used for calculation for either specific inventory database item
or specific decommissioning activity in the PSL structure. <strong>The</strong> new verification module allows compare selected input
parameters to reference values including graphic display of differences. <strong>The</strong>re is also a possibility to perform
recalculation of the some decommissioning option using reference values of input data and consequently to compare
calculated decommissioning data. <strong>The</strong>se data (e.g. exposure, labor, and cost) and their differences can be compared both
in tables and graphs, for either specific inventory database item or specific PSL activity. <strong>The</strong> verification module within
the OMEGA Code brings a new view on impact of selected input data change on calculated decommissioning data. It is
auxiliary tool for contingency calculation using analytical methods developed last year.
3) 40078 – Experience of MR and RFT Reactors’ Decommissioning in RRC “Kurchatov Institute”
Alexander V. Chesnokov,Victor Volkov, Sergey Semenov, Vitaly Pavlenko, Vyacheslav Kolyadin,
D. Muzrukova, RRC "Kurchatov Institute" (Russia);Artur Arustamov, SUE SIA "Radon" (Russia)
Research channel-type nuclear reactor «MR» has been developed and commissioned in Russian Research Centre
«Kurchatov Institute» in 1962-1963. "MR" reactor replaced the old one -"RTF" type reactor. MR is one of 12 units
located in Kurchatov Institute. It started the operation in 1963, and shut down in 1992. Reactor is located in the water
pool on the 9 m depth. Nine loop units with different cooling medium are the experimental basis of MR. When MR has
been shut down; the loop channels were disconnected and placed into water pool. Nuclear fuel has been unloaded and
moved to the dry repository. Decommissioning design has been developed by Russian Research Centre «Kurchatov
institute» and JSC «Alliance-Gamma» in 2009 year. According to the decommissioning design the final state of reactor
MR will come to: - Equipment and systems of reactor shall be dismantled completely; - Technological facilities of
reactor and MR territory shall be decontaminated and remediated according to the regulations. D&D design has been
approved by Russian Authority in July 2009 year. In August 2009 the equipment supply and preliminary works have
been started. Dismantling works are scheduled to start in 2011. Features of the reactor MR which have made an essential
impact on the development of the project on decommissioning are shown. A status on decommissioning of reactors MR
and RTF is resulted. <strong>The</strong> work performed on the reactor MR in preparation for decommissioning, which include: removal
of irradiated fuel from near reactor storage, disposal units of loop channels, acting above the water surface in a pool
storage are described, identification, sorting and disposal of radioactive objects from gateway of the reactor is carried out.
<strong>The</strong> technologies for dismantling works were identified and the stages of work on the decommissioning of reactors MR
and RTF is presented. <strong>The</strong> assessment of radiation effects on the population and the environment during the dismantling
operations, which is determined by the amount of dismantling operations, the level of radioactive contamination of the
reactor structures and equipment, as well as the technologies used for their removal is completed. <strong>The</strong> results of the
estimation of radiation effects on the population and the environment during routine operation to dismantle the
equipment and in emergency situations are reduced.
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