Thermal hydraulic studies of liquid-metal coolants in nuclear-power facilities

We present the results of experimental, numerical, and theoretical thermal hydraulic studies at the SSC IPPE aimed at substantiation of designs of nuclear-power facilities with liquid-metal coolants. The fundamental studies cover the physical basics of hydrodynamics and heat transfer in the channels of nuclearpower facilities, the development of the theory and numerical methods, as well as codes and code verification based on the experiments. The results of applied studies of fuel-element bundles are obtained while considering the influences of various geometric and mode factors (fuel-element energy release, the coolant-flow rate through fuel assemblies, specific features of the assembly geometry, assembly casings, separate fuel elements, fuel pellets, displacers, etc.), including parameter variation during the lifetime of a facility due to temperature inhomogeneities, radiation swelling, radiation creep, etc.