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核电厂安全壳内操作平台火灾概率安全分析研究

Study on Fire Probability Security Analysis of Operating Platform Inside the Containment in Nuclear Power Plant
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摘要 安全壳内操作平台是核电厂火灾风险评价的重要内容之一。本文对典型核电厂的安全壳内操作平台进行火灾风险分析,使用事件树方法演绎分析火灾情境并确定火灾情境的危害,通过对核电厂安全壳内火灾操作平台火灾序列演绎分析,建立安全壳操作平台火灾概率安全分析模型,进行定量化评估。研究分析3个火灾情境对核电厂始发事件和系统设备的影响。风险定量化结果表明:安全壳内操作平台火灾导致的堆芯损坏频率为3.11×10^(-8)/(堆·年)。 Operating platform inside the containment is one of the important contents of nuclear power plant fire risk assessment. In this paper, the risk analysis of fire between Operating platform inside the containment in typical NPPs is carried out. Based on the deductive analysis of the fire sequence of the containment platform in nuclear power plant, the probabilistic safety analysis model of the containment platform fire is established and evaluated quantitatively. The influence of three fire scenarios on the initial event and system equipment of nuclear power plant is analyzed. Risk quantification results show that the frequency of core damage caused by fires between Operating platform inside the containment is 3.11×10^(-8)/(reactor·year).
作者 史强 石兴伟 贾斌 张泽宇 王逊 SHI Qiang;SHI Xingwei;JIA Bin;ZHANG Zeyu;WANG Xun(Nuclear and Radiation Safety Center,MEP,Beijing,102488,China)
出处 《核科学与工程》 CAS CSCD 北大核心 2022年第6期1455-1459,共5页 Nuclear Science and Engineering
关键词 安全壳内操作平台 火灾风险分析 火灾情境 堆芯损坏频率 Operating platform inside the containment Fire risk assessment Fire scene analysis Core damage frequency
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  • 1U.S.NRC /EPRI.Fire PRA Methodology for NuclearPower Facilities[R].NUREG/CR-6850 Vol.2.Sep.2005. 被引量:1
  • 2濮继龙.大亚湾核电站运行教程(下)[M].北京:原子能出版社,1998. 被引量:2
  • 3中国国家核安全局.HAF102.核动力厂设计安全规定[S].2004. 被引量:1
  • 4中国国家核安全局.HAF103.核动力厂运行安全规定[S].2004. 被引量:1
  • 5IAEA.Experience gained from fires in nculear power plants:lessons learned. IAEA-TECDOC-1421 . 2004 被引量:1
  • 6EPRI.Fire PRA methods enhancements:addi-tions,clarifications and refinements to EPRI1019189. EPRI1016735 . 2008 被引量:1
  • 7Nowlen S P,Kazarians D M,SWyant F.Risk methods insights gained from fire incidents. NUREG/CR-6738 . 2001 被引量:1
  • 8IAEA.Safety Series No.50-P-4Procedures for conducting probabilistic safety assessments for nuclear power plants. . 1992 被引量:1
  • 9IAEA.Treatment of internal fires in prboabilistic safety assessment for nuclear power plants. Safety Reports Series No.10 . 1998 被引量:1
  • 10IAEA.Regulatory review of probabilistic safety assessment(PSA)Level1. IAEA-TECDOC-1135 . 2000 被引量:1

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