28th Symposium of AER on VVER Reactor Physics and Reactor Safety (2018, Olomouc, Czechia)
Fuel management issues
R. Zajac, M. Majerčík (VÚJE)
VVER-440 reactors have been utilized in Slovakia since 1978. So far, the vast majority of their core loadings were designed in VUJE institute. This paper presents a description of the methods and procedures, which have been used on this purpose in the last decade. Main attention is focused on the calculating tools for core refuelling scheme optimization.