Source Term Determination for VVER‐440/V230 Reactor Decommissioning by MCNP5, Slovak University of Technology in Bratislava
26th Symposium of AER on VVER Reactor Physics and Reactor Safety (2016, Helsinki, Finland)
Intermediate storage of spent fuel decommissioning and radwaste / Spent fuel disposal and actinide transmutation
Abstract
SOURCE TERM DETERMINATION FOR VVER-440/V230 REACTOR DECOMMISSIONING BY MCNP5Martin Oravkin, Kristína Krištofová, Gabriel Farkas, Vladimír SlugeňSlovak University of Technology, Faculty of Electrical Engineering and Information Technology, Institute of Nuclear and Physical Engineering, Ilkovicova 3, 812 19 Bratislava, Slovakiamartin.oravkin@stuba.skABSTRACTThe main objective of the paper is to present calculated neutron source term results for a selected VVER440/V230 core configuration representing the first 12 campaigns of the V1 NPP at Jaslovské Bohunice site. Non-profiled fuel assemblies with steel spacer grids and relevant spatial burnup and coolant temperature distributions were taken into account for the campaign as well as the other integral core parameters, based on operational records.Transport Monte Carlo code MCNP5 with ENDF/B-VII.1 cross section libraries was applied to calculate the neutron source term on the core boundary and its characteristics.The determined source term is planned to be used for future transport calculation in order to evaluate the reactor induced activity (internal and external structural components) for the purpose of its decommissioning. The final major task will be a validation of calculated results with the experimental ones. 26th Symposium of AER on VVER Reactor Physics and Reactor Safety 56 10 – 14 October 2016, Helsinki, Finland