美国三级PSA发展过程及研究进展

摘要/Abstract

摘要： 公众风险是验证核电厂安全性能的重要指标。美国1957年发布的WASH-740中开始引入反应堆风险分析的概念;1972年,WASH-1400第一次系统性地完成了三级PSA,并开发了CRAC系列分析程序;1990年,NRC发布NUREG-1150,标志着PSA应用进入成熟期;1995年,正式在法规层面上确定了PSA地位;始于2007年的SOARCA研究计划在SARP研究基础上,结合最新研究进展利用改进的三级PSA工具对两个核电厂重新进行了评估;2011年,考虑最新的技术进步和福岛事故影响,计划重新启动完整三级PSA研究,以考虑如乏燃料水池工况、群堆工况、外部事件等新的认识。

关键词: 核电厂, 概率安全分析, 风险评价

Abstract: Public risk is an important index of Nuclear Power Plant (NPP) safety. WASH-740, which was issued in 1957, started introducing the concept of reactor risk analysis. In 1972, WASH-1400 accomplishedsystematically a Level 3 PSA for the first time, and gave rise to the development of CRAC series codes. Furthermore, NUREG-1550 was published in 1990, which indicated PSA application matured. NRC established the current framework for risk-informed regulation by issuing a PRA Policy Statement in 1995. In 2007, The SOARCA project was initiated to develop best estimates of the offsite radiologicalhealth consequences for potential severe reactor accidents for Peach Bottom Atomic Power Station and Surry Power Station. In 2011, NRC proposed to perform a new full-scope comprehensive Level 3 PSA which addressed additional considerations such as multi-unit site effects and other on-site radiological sources.

Key words: Nuclear power plant, Probabilistic safety analysis, Risk assessment

中图分类号:

TL364⁺5

王建华, 陈鹏, 杨杰, 苏永杰. 美国三级PSA发展过程及研究进展[J]. 辐射防护通讯, 2015, 35(6): 7-12.

Wang Jianhua, Chen Peng, Yang Jie, Su Yongjie. The Developing Process and Study Trends of Level 3 PSA in USA[J]. RADIATION PROTECTION BULLETIN, 2015, 35(6): 7-12.

参考文献

[1] NRC. Reactor Safety Study: An Assessment of Accident Risksin U.S. Commercial Nuclear Power Plants[R]. WASH-1400, NUREG-75/014, Washington: NRC, 1975.
[2] IAEA. Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants (Level 3)[R]. SSR-050-P-12, Vienna: IAEA, 1996.
[3] Kelly G N, Olast M, Sinnaeve J. The CEC Research Program onMethods for Assessing the Radiological Impact of Accidents (MARIA)[J]. Nuclear Technology, 1991,94(2):161.
[4] IAEA. The Role of Probabilistic Safety Assessment and Probabilistic Safety Criteria in Nuclear Power Plant Safety[R]. SSR No.106, Vienna:IAEA, 1992.
[5] AEC. Theoretical Possibilities and Consequences of Major Accident in Large Nuclear Power PlantsAtomic Energy Commission[R]. ORNL-3441, Washington: AEC, 1957.
[6] NRC. Code Manual for MACCS2 User's Guide[Z]. NUREG/CR-6613, Washington: NRC, 1998.
[7] NRC. CRAC2 Model Description[R]. NUREG/CR 2313, Washington, NRC, 1984.
[8] NRC. MELCOR Accident Consequence Code System (MACCS), Programmer's Reference Manual[R]. NUREG/CR-6613, Washington:　NRC, 1990.
[9] NRC. Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants[R]. NUREG-1150, Washington: NRC, 1990.
[10] 濮继龙. 压水堆核电厂安全与事故对策[M]. 北京:原子能出版社, 1995.
[11] NRC. Use of Probabilistic Risk Assessment Methods in Nuclear Regulatory Activities[R]. 60 FR 42622, Washington: NRC, 1995.
[12] NRC. Safety Goals for the Operations Nuclear Power Plants; PolicyStatement[R]. 51 FR 30028, Washington: NRC, 1986.
[13] NRC. An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis[R]. RG 1.174, Washington: NRC, 2011.
[14] OECD/NEA. Probabilistic Accident Consequence Assessment Codes - Second International Comparison, Overview Report[R]. Paris: OECD, 1994.
[15] CEC. Probability Accident Consequence Assessment Codes - Second International Comparison[R]. Luxembourg: CEC, 1993.
[16] CEC. COSYMA: Users Intercomparison Exercise[R]. Luxembourg: CEC,1993.
[17] NRC. Comparison of MACCS Users Calculations for the InternationalComparison Exercise on Probabilistic Accident Consequence Assessment Codes[R].NUREG/CR-6053, Washington: NRC, 1993.
[18] NRC. State-of-the-Art Reactor Consequence Analyses (SOARCA) Report[R]. NUREG-1935, Washington: NRC, 2012.
[19] NRC. Options For Proceeding With Future Level 3 Probabilistic RiskAssessment Activities[R]. SECY-11-0089, Washington: NRC, 2011.
[20] NRC. Regulatory Analysis Guidelines of the U.S. Nuclear RegulatoryCommission[R]. NUREG/BR-0058, Washington: NRC, 2004.
[21] NRC. Regulatory Analysis Technical Evaluation Handbook[R]. NUREG/BR-0184, Washington: NRC, 1997.
[22] NRC. Feasibility Study for a Risk-Informed and Performance-BasedRegulatory Structure for Future Plant Licensing[R]. NUREG-1860, Washington:NRC, 2007.
[23] NRC. Potential Policy, Licensing, and Key Technical Issues for Small Modular Nuclear Reactor Designs[R]. SECY-10-0034, Washington: NRC, 2010.
[24] NRC. Use of Risk Insights to Enhance the Safety Focus of Small Modular Reactor Reviews[R]. SECY-11-0024, Washington: NRC, 2011.
[25] NRC. Modifying the Risk-Informed Regulatory Guidance for New Reactors[R]. SECY-10-0121, Washington: NRC, 2010.