Calculation and experimental analysis of benchmark experiments with a fast neutron spectrum and models of sodium and lead cooled fast reactors using different evaluated nuclear data libraries

The paper presents the results of a comparative analysis criticality calculations using Monte-Carlo code with BNAB-93 and BNAB-RF neutron group constants, as well evaluated data files from Russian ROSFOND nuclear library other libraries (ENDF, JEFF, JENDL) different years. A set integral experiments on BFS critical assemblies carried out in years at Institute Physics Power Engineering (60 configurations) was analyzed. considered are included database experimental neutronic used to justify performance sodium lead cooled fast reactors, verify codes estimate uncertainties parameters due uncertainties. It has been shown that is minimizes calculation discrepancies for experiments. also models reactors based provides estimates uncertainty associated data.