SYSTEM OF CODES FOR PHYSICAL DESIGN OF THE LEAD-COOLED FAST REACTOR

One of the actual task at present is the substantiation of the project of the pilot demonstration reactor with a lead coolant BREST-OD-300. For the implementation of large-scale development of nuclear power, which meets modern requirements for new generation reactors, a competitive commercial power unit BR-1200 with an electric capacity of 1200 MW is being designed. To solve complex problems in the study for the optimal configurations of the core, it is required to develop a system of design codes that allows us to perform works on physical design and safety justification. System of codes includes the diffusion software package FACT-BR, the precision software package MCU-BR and the thermos-physical module IVIS-BR. The system is designed to conduct accurate studies of the physical characteristics during the design and computational support of a fast reactor with a lead coolant operating in a closed nuclear fuel cycle. The article provides a brief description of the system of codes. To demonstrate the capabilities of the system of codes, test calculation of the BR-1200 core was carried out.