“…As a result of integrated studies, the code used for combined neutron-physical and thermohydraulic calculations of VVER-SKD was improved, the use of one-and two-loop working sections with supercritical water in a closed fuel cycle was analyzed, the thermal scheme chosen for a nuclear power plant with VVER-SKD-1600 was evaluated and optimized, the stress-strain state of a fuel element with oxide fuel was evaluated for the conditions of VVER-SKD operation, the normal and degraded heat-exchange regimes were studied, and the method and MIF-SKD code for calculating the thermohydraulic parameters of the reactor core taking account of different factors and parameter uncertainties were improved [10,11].…”