| 关于核电厂火灾概率风险的研究 |
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| 引用本文： | 孙凤,赵庆南,张志俭.关于核电厂火灾概率风险的研究[J].原子能科学技术,2017,51(5):872-878. |
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| 作者姓名： | 孙凤 赵庆南 张志俭 |
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| 作者单位： | 1.哈尔滨工程大学 核安全与仿真技术国防重点学科实验室，黑龙江 哈尔滨150001；2.中国核电工程有限公司，北京100840 |
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| 摘 要： | 火灾是核电厂安全面临的重要威胁之一。应用概率风险评价(PRA)方法对其进行分析,能找出电厂薄弱环节,优化电厂的设计。通过研究国际广泛使用的火灾PRA方法,以典型的二代压水堆核电厂为对象,开展了火灾概率风险分析,计算得到了火灾引起的堆芯损坏频率(CDF)为4.03×10-6(堆·年)-1。在此基础上,开展了敏感性分析,讨论了人因事件和定量筛选值对结果的影响。
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| 关 键 词： | 火灾 概率风险评价 堆芯损坏频率 |
Research on Fire PRA for NPPs |
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| SUN Feng,ZHAO Qing-nan,ZHANG Zhi-jian.Research on Fire PRA for NPPs[J].Atomic Energy Science and Technology,2017,51(5):872-878. |
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| Authors: | SUN Feng ZHAO Qing-nan ZHANG Zhi-jian |
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| Affiliation: | 1.Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin 150001, China; 2.China Nuclear Power Engineering Co., Ltd., Beijing 100840, China |
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| Abstract: | Fire is one of the threats to nuclear power plant safety.Fire analysis, using probabilistic risk assessment (PRA), can find out the weakness of the plant and improve its design.Based on the study on fire PRA methodology widely used across the world, the fire PRA was developed for a typical second-generation pressurized water plant.The results show that the core damage frequency induced by fire is 4.03×10-6(reactor·year)-1.After that, the sensitivity analysis was performed, and the influence of human error and quantitative screening value were discussed. |
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| Keywords: | fire probabilistic risk assessment core damage frequency |
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