Nuclear Criticality Safety Analysis of Wet Interim Storage Pool Using Mcnp5, Slovak University of Technology in Bratislava

G. Farkas (Mr), Institute of Nuclear and Physical Engineering

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

NUCLEAR CRITICALITY SAFETY ANALYSIS OF WET INTERIM STORAGE POOL USING MCNP5Gabriel Farkas, Vladimír Slugeň, Branislav Vrban, Jakub LüleySlovak University of Technology, Faculty of Electrical Engineering and Information Technology, Institute of Nuclear and Physical Engineering, Ilkovicova 3, 812 19 Bratislava, Slovakiagabriel.farkas@stuba.skABSTRACTThe paper presents results of nuclear criticality safety analysis of wet interim storage pool, located at Jaslovské Bohunice site. One of four pools loaded with non-compact T-12 respectively compact KZ-48 casks was modeled in MCNP5 code. The storage casks were filled with the II. Gen 4.87 % enr. fuel assemblies at different burnup levels. Conservative approach was applied and calculation of keff values was performed for normal and various postulated emergency conditions in order to evaluate the final maximal keff values. The requirement of current safety regulations to ensure 5% subcriticality was met in all investigated conservative cases. 26th Symposium of AER on VVER Reactor Physics and Reactor Safety 58 10 – 14 October 2016, Helsinki, Finland

Presentation / full paper