A study of residual heat from a VVER-640 reactor for accidents with losses of primary-circuit coolant

The specifics of the thermal and hydraulic processes in cooling a VVER-640 reactor using the emergency pool in the final stage of a design-basis accident with a loss of the primary-circuit coolant are considered. A brief description of the code PARNAS is given. This code is used for analyzing processes in removing the residual heat of the reactor to the terminal heat sink through natural circulation of the coolant. The results from verifying the code are presented.