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多堆PSA机组间共因失效分析研究

Research on Inter-unit Common Cause Failure of Multi-unit PSA

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合理评估同一厂址内不同机组间共因失效(CCF)对电厂安全风险的贡献是多堆概率安全分析(PSA)建模中需要解决的重要技术问题.本研究对设备机组间CCF组的选取、CCF建模和参数估计的方法进行梳理,并以具有4台机组的某压水堆核电厂丧失厂外电(LOOP)事件为分析案例,定量评估在考虑设备机组间CCF前后的多堆PSA模型堆芯损坏频率(CDF)变化情况.研究结果表明,在考虑设备机组间CCF后,多堆PSA结果中仅有一台机组发生堆芯损坏(CD)的频率和多台机组同时发生CD的频率均会有所增加.由此可见,机组间CCF对多堆PSA结果有一定影响.
How to reasonably estimate the contribution of inter-unit common cause failure(CCF)to the safety risk of power plant is an important technical problem that needs to be solved in multi-unit probabilistic safety analysis(PSA)modeling.In this study,analysis methods of inter-unit CCF group selection,modeling and parameter estimation are presented,and the loss of offsite power(LOOP)event of a four-unit pressurized water reactor(PWR)nuclear power plant is taken as an analysis case to quantitatively evaluate the change of core damage frequency(CDF)of multi-unit PSA model before and after considering CCF.The results show that after considering the inter-unit CCF,the frequency of core damage(CD)occurrence in only single unit and the frequency of CD occurrence in multiple units will increase.It can be seen that inter-unit CCF has a certain effect on multi-unit PSA results.

Multi-unitProbabilistic safety analysis(PSA)Common cause failure(CCF)analysisCore damage frequency(CDF)

杨春菊、王明、林模悌、张冰、王金凯

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核电安全技术与装备全国重点实验室,中广核工程有限公司,广东深圳,518172

多堆 概率安全分析(PSA) 共因失效(CCF)分析 堆芯损坏频率(CDF)

2024

核动力工程
中国核动力研究设计院

核动力工程

CSTPCD北大核心
影响因子:0.3
ISSN:0258-0926
年,卷(期):2024.45(2)