Development of conceptual proposal for a nuclear facility with the gas cooled fast reactor BGR-1000 using coated micro-fuel and technologies of light water reactors

The paper presents the status in elaboration of a reactor facility with a Gas Cooled Fast Reactor named BGR-1000 on the initial stage of developments. In the present time, general formulation of the concept is given and analysis of possible design decisions for the active core and first circuit equipment is performed. The design of a reactor facility with the fast helium cooled reactor 1000 MWe is based on the active core with fuel assemblies containing the fixed bed of coated fuel microparticles directly cooled by cross flow of helium coolant with moderate (750 o C) outlet temperature. The neutron-physics characteristics of this reactor and their connection with the parameters of the core layout and fuel cycle options are preliminary evaluated. Preliminary assessments are performed for thermal-hydraulic characteristics, fuel behavior analysis, etc.