Aktivní a pasivní bezpečnostní systémy jaderného bloku VVER 1200 Rosatom

Abstract

The bachelor thesis deals with an analysis of active and passive safety systems of the VVER1200 Rosatom nuclear reactor, which is one of the possible projects for finishing new reactors in the Czech Republic. In this thesis, a basic system of a nuclear power station is described, including the risks connected with this plant. The classification and description of individual technological units creating the safety system of the VVER 1200 nuclear reactor follow. The computing part deals with the horizontal water-water reactor heat output PGV-1000MKP.