压水堆核电厂气液态放射性流出物源项计算程序CPGale的开发

Abstract

Abstract: Following the analysis on the generation and discharge mechanism of radioactive gaseous and liquid effluents during normal operation of pressurized water reactor nuclear power plant, the calculation model is improved and the calculation code CPGale with good man-machine interface is developed. The CPGale code is validated by operation data of in-service nuclear power plant in China. The validation result shows that the radioactive gaseous and liquid effluent source term calculated by CPGale code has an appropriate conservation compared with the operation data of in service nuclear power plant. The CPGale code can fulfill the requirements of nuclear power plant design and can be used in engineering applications.

Key words: radioactive effluent, source term, pressurized water reactor nuclear power plant

CLC Number:

TL75

LV Weifeng, CHEN Mingliang, LIU Jie, XIONG Jun, JIANG Zhenyu. The development of calculation code CPGale for radioactive effluent source term of pressurized water reactor nuclear power plant[J].RADIATION PROTECTION, 2022, 42(5): 425-432.

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The development of calculation code CPGale for radioactive effluent source term of pressurized water reactor nuclear power plant

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