Amine Bouhaddane, Gabriel Farkas, Vladimír Slugeň, Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Institute of Nuclear and Physical Engineering

23rd Symposium of AER on VVER Reactor Physics and Reactor Safety (2013, Štrbské Pleso, Slovakia)
Spent fuel storage and disposal


The paper briefly describes the issue of radionuclide inventory determination in
decommissioned nuclear power plants with emphasis on the VVER-440 reactor type.
According to radionuclide inventory calculation, it is possible to optimize the time frame and
choose the appropriate dismantling procedure during the disposal of reactor internal and
external components during the decommissioning phase of a nuclear power plant. Due to high
technological and financial demands in the case of in situ measurements or sampling, it is
important to use validated code systems to precisely estimate the radionuclide inventory.
Prerequisite for a correct calculation is the collection of reactor operation data. In this paper,
abilities of MCNPX code in this field is presented on the example of calculation for the
shielding (dummy) elements used in V-230 reactor in Jaslovsk? Bohunice Nuclear Power
Plant. These elements were installed into the reactor core in order to protect the reactor
pressure vessel from high neutron flux. They also represent the most activated component of
the reactor.

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