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

摘要

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.