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

被引:0
|
作者
Monev, Vladimir M. [1 ]
Filipov, Kalin B. [2 ]
机构
[1] Kozloduy Nucl Power Plant, Kozloduy, Bulgaria
[2] Tech Univ Sofia, Dept Thermal & Nucl Power Engn, Sofia, Bulgaria
关键词
Nuclear power plant; steam generator; heat transfer; simulation modelling; nuclear safety; MATLAB;
D O I
10.1109/EFEA49713.2021.9406229
中图分类号
X [环境科学、安全科学];
学科分类号
08 ; 0830 ;
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.
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页数:6
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