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Reliability Analysis of the Passive Residual Heat Removal System for Large Advanced Pressurized Water Reactors
编号：68
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更新：2024-09-08 17:37:04 浏览：162次
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摘要
This paper focuses on the passive residual heat removal system of a typical large advanced pressurized water reactor, analyzing its design, performance, and reliability under station blackout conditions coupled with the failure of the auxiliary feedwater steam-driven pumps. The study employs modeling of passive safety systems and utilizes response surface methodology to evaluate system behavior during severe accident scenarios. Such comprehensive analysis contributes to ensuring the safe operation and advancement of nuclear power plants. The best-estimate program VITARS is used to analyze and calculate accident scenarios, with sensitivity analysis conducted based on preliminary thermal-hydraulic calculations to optimize parameter selection and simplify the response surface model structure, thereby streamlining the analysis process. An artificial neural network is employed as a surrogate model for complex thermal-hydraulic calculations, significantly improving analysis efficiency. The findings indicate that the passive residual heat removal system has zero failure probability under normal uncertainty ranges within 72 hours. Even under extreme conditions, such as delayed opening of the steam generator's safety valve, the system maintains reactor safety with a failure probability of only 0.035%.
关键词
Passive residual heat removal system,Response surface,Artificial neural network
报告人
Tianrui Li
Xi'an Jiaotong University稿件作者
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重要日期
-
会议日期
09月23日
2024
至09月25日
2024
-
09月24日 2024
报告提交截止日期
-
09月25日 2024
注册截止日期
主办单位
Harbin Engineering University (HEU)
联系方式
- Prof. WANG Xiang
- xi******@hrbeu.edu.cn
历届会议
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2016年09月26日 中国 Chengdu,China
8th International Symposium on Symbiotic Nuclear Power Systems for 21st Century -
2016年09月26日 中国 Chengdu,China
第八届21世纪和谐核电系统国际会议 -
2010年08月23日 中国 哈尔滨市
第三届21世纪和谐核电系统国际会议（ISSNP2010）
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