IMPLEMENTATION OF COMPARATIVE BURNUP CALCULATIONS

Abstract

Features of calculation methods implemented in computer codes, evaluated nuclear data libraries and computer models have a significant impact on the results of burnup calculations. This article contains comparative calculations of VVER-1000 reactor nuclear fuel burnup and demonstrates an influence of different factors on the results of these calculations. The results of comparative analisys demonstrate the necessity to intensify creation of benchmarks with experimental data on nuclide concentarions in fuel including fuel for fast neutron reactors.