Mathematical modeling of steamgeneator PGV-1000, used in nuclear power plant with WWER-1000 nuclear reactor

Proper operation of steam generators in nuclear power plants is critical for the nuclear safety. In this research is developed simplified mathematical model of steam generator PGV-1000, used in eastern-type pressurized water reactors WWER-1000. The mathematical model uses an interpolation between the primary quantities in the primary loop, which can be used to solve the heat transfer problem under non-nominal operational conditions. The accumulation of deposits over the tube bundle and the tube failure in the tube bundle are analyzed.