Neutron codes for calculating advanced reactor plants with a liquid metal coolant

Abstract

Numerical simulation based on contemporary computational codes represents a current trend for the safety justification of existing and planned nuclear power facilities including reactor plants with liquid metal coolants. The present study considers neutron codes developed by IBRAE RAN under the Proryv project direction. The paper discusses CORNER and ODETTA codes based on the discrete ordinate method, the BPSD code for isotope kinetics, activity and decay heat calculation, EVKLID/V1 and EVKLID/V2 integral codes, as well as the COMPLEX software system for substantiating nuclear and radiation safety.