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CAP1400核电站非能动安全壳冷却系统综合性能试验研究 被引量:3

Thermal Hydraulic Tests for CAP1400 Passive Containment Cooling System
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摘要 CAP1400非能动安全壳冷却系统(Passive Containment Cooling System,PCS)仍采用与AP600和AP1000相同的先进非能动设计理念。本研究针对CAP1400的非能动安全壳冷却系统,设计并建造了非能动安全壳冷却系统综合性能试验平台(Containment safety vErification via integRal Test facility,CERT),开展了试验研究。对CAP1400非能动安全壳冷却系统综合性能试验验证需求,试验装置的设计特点、研究内容及代表性的试验结果进行了介绍。通过PCS综合性能试验的开展,研究了非能动安全壳冷却系统的事故响应特性及关键物理现象,为CAP1400的安全评审及相关安全分析程序验证提供了试验结果支撑。 CAP1400 passive containment cooling system (PCS), which is still based on the design concept of the AP600/1000 passive safety technology. To verify the design of CAP1400 PCS, one large-scale integral test facility (CERT) was designed and built to carry out the PCS test verification of CAP1400. In this paper, the overall test verification requirements of CAP1400 passive containment cooling system, the design features of CERT facility, and the research contents and representative test results are introduced. Based on the test results and analysis, accident response and critical physical phenomenon are studied. The research results provide valuable support for CAP1400 safety review and related safety analysis code validation.
作者 常华健 高彬 赵瑞昌 范普成 周明正 常磊 施文博 CHANG Hua-jian;GAO Bin;ZHAO Rui-chang;FAN Pu-cheng;ZHOU Ming-zheng;CHANG Lei;SHI Wen-bo(Guohe Huaqing (Beijing) nuclear power technology r&d center Co. Ltd.,Beijing 102200,China;TsinghuaUniversity,Beijing 100084,China)
出处 《中国核电》 2019年第1期31-35,共5页 China Nuclear Power
基金 国家科技重大专项资助 课题编号:2015ZX06002007
关键词 非能动安全壳冷却系统 热工水力试验 CAP1400 passive containment cooling system thermal hydraulic experiment CAP1400
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