Criticality safety analysis of fresh and spent fuel storage and handling for NPP Mochovce using MCNP5

G. Farkas, J. Haščík, J. Lüley, B. Vrban, M. Petriska, V. Slugeň, P. Urban, Slovak University of Technology in Bratislava, Slovakia

21st Symposium of AER on VVER Reactor Physics and Reactor Safety (2011, Dresden, Germany)
Spent fuel disposal, actinide transmutation

Abstract

The paper presents results of nuclear criticality safety analysis of spent fuel storage for the 1st
and 2nd unit of NPP Mochovce. The spent fuel storage pool (compact and reserve grid) was
modeled using the Monte Carlo code MCNP5. 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 except one especially conservative case.

Presentation / full paper