Thermal-hydraulic researches of safety problems in fast breeder reactors

摘要

The researches on thermophysical validation of nuclear facility safety as applied to fast reactor with sodium cooling are performed for a wide range of problems including the thermohydraulics of reactor core and individual subassemblies, transient processes with mixed and natural convection of the coolant within reactor vessel, as well as in the individual subassemblies, processes in the upper chamber including interaction of coolant jets above subassembly heads, temperature pulsations in the coolant and in structure elements, gas capture from sodium surface in reactor gas volume and its transport along facility piping, influencing of blockage of a part of a flow area subassembly, processes of heat and mass transfer connected with generation, transport, deposition and accumulation of impurities in sodium loops and protective gas in fast reactor facilities, vibration stability in structure elements, onset and development of sodium boiling, sodium-water interaction, sodium fires in case of loss of pressure in circulation loops and generation of aerosols, corium-sodium interaction in case of fuel melting during heavy accident and steam explosion.