Comparison of determined MCNP neutron source terms for VVER‐ 440/V230 decommisioning, 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
COMPARISION OF DETERMINED MCNP NEUTRON SOURCE TERMS FOR VVER-440/V230 DECOMMISSIONINGKristína Krištofová, Gabriel Farkas, Martin Oravkin, Vladimír SlugeňSlovak University of Technology, Faculty of Electrical Engineering and Information Technology, Institute of Nuclear and Physical Engineering, Ilkovicova 3, 812 19 Bratislava, Slovakiakristina.kristofova@kind-consultancy.comABSTRACTThe paper presents a comparison of different neutron source terms, determined for given VVER440/V230 core configurations, related to operational history of the V1 NPP at Jaslovské Bohunice site. The main objective was to determine the influence of diverse core characteristics, such as loading pattern, fuel assembly (FA) types, and presence of shielding assemblies (SA) on given source term (spatial, energy, and angular distribution of neutron flux at surface source boundaries). Four typical operational periods were distinguished: non-profiled FAs with steel spacer grids, non-profiled FAs with loaded shielding assemblies, non-profiled FAs with zirconium spacer grids and SAs, and profiled FAs together with SAs. Corresponding spatial burnup and coolant temperature distributions were taken into account for the selected campaigns as well as other integral core parameters, based on operational records. Transport Monte Carlo system MCNP5 with ENDF/B-VII.1 cross section libraries was applied to calculate the neutron source term on the core boundary and its characteristics.This resulted to a selection of reference core characteristics and relevant number of neutron source terms to be used in the following transport calculation and subsequently to evaluate the reactor activation for the purpose of its decommissioning. The final goal is to validate calculated results with experimental samples and use the validated model for VVER 440/V213 activation calculations, as well.26th Symposium of AER on VVER Reactor Physics and Reactor Safety 57 10 – 14 October 2016, Helsinki, Finland
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