Abstract
The paper presents results of neutronic parameter calculations of experimental device intended for studying processes of core materials melt movement into the area with restricted amount of coolant – sodium melt – and its cooling with presence of residual energy release in the melt. Calculated values of energy release distribution along the height of model fuel assembly have been obtained. The value of ratio of energy release in melt and structural materials of the experimental device to the energy release in the reactor core have been estimated.