Methodical specifics in substantiating passive safety systems for nuclear pwer stations with VVER-640 reactors

The specifics of the project for a new-generation nuclear power station with a VVER-640 reactor having passive safety systems are considered. A brief analysis of the results of the research and development that was carried out in substantiating the fact that the nuclear power station is safe is presented. The necessity of constructing a large-scale integral testing facility (LSTF) that can be used for the comprehensive simulation of interrelated processes in the reactor installation, the containment unit, and the safety systems is shown.