设备地震易损性分析方法研究
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摘要
地震PSA可以找到核电站在地震中的薄弱环节,是评价地震对核电厂影响的一种有效的方法,易损性分析是其中重要的一个步骤。本文介绍了设备地震易损性的概念,给出了地震易损性的数学模型,讨论了设备在地震情况下的失效模式判定问题,重点研究了易损性参数及其量化的两种方法:基于分析的方法和基于测试的方法,最后得出中值易损性、随机性和不确定性分布以及HCLPF(高可信度低失效概率)能力的计算公式。另外,设备地震易损性分析需要使用真实地震经验数据、测试数据和分析数据,这些都需根据特定电厂的需要进行收集和完善。
Vulnerable points of nuclear power plants can be found through seismic PSA which is an effective method to evaluate the seismic effect on nuclear power plants,and fragility analysis is one important step for seismic PSA.In this paper,the concept of seismic equipment fragility is introduced,the mathematic model of seismic fragility is given,the determination of equipment failure modes is discussed,fragility analysis variables and methods(i.e.method based-on analysis and method based-on dynamic testing)are mainly studied,and finally median fragility,the distribution of randomness and uncertainty and HCLPF capacity can be calculated by formulations.On the other hand,when developing seismic fragility,there are three types of information that can be relied on:data from real earthquake experience,test data and analysis data,and this data used in specific nuclear plant need to be collected and completed.
Vulnerable points of nuclear power plants can be found through seismic PSA which is an effective method to evaluate the seismic effect on nuclear power plants,and fragility analysis is one important step for seismic PSA.In this paper,the concept of seismic equipment fragility is introduced,the mathematic model of seismic fragility is given,the determination of equipment failure modes is discussed,fragility analysis variables and methods(i.e.method based-on analysis and method based-on dynamic testing)are mainly studied,and finally median fragility,the distribution of randomness and uncertainty and HCLPF capacity can be calculated by formulations.On the other hand,when developing seismic fragility,there are three types of information that can be relied on:data from real earthquake experience,test data and analysis data,and this data used in specific nuclear plant need to be collected and completed.
引文
[1]R.Kassawara,et al.Seismic Probabilistic RiskAssessment Implementaton Guide[R].EPRI 1002989,Electric Power Research Institute(EPRI),Palo Alto,California,2003.
[2]M.P.Bohn,J.A.Lambright,Severe Accident Risk,An Assessment of Five US Nuclear Power Plants[R].NUREG-1150,Volumes 1and 2,1990.
[3]Jack R,et al.Methodlogy for Developing SeismicFragilities[R].EPRI TR-103959,Electric PowerResearch Institute(EPRI),Palo Alto,California,1994.
[4]J.Hickman,et al.PRA Procedures Guide:A Guide tothe Performance of Probabilistic Risk Assessments forNuclear Power Plants[S].NUREG/CR-2300,American Nuclar Society,Institute of Electrical andElectronic Engineers,and U.S.Nuclear RegulatoryCommissin,1983.
[5]R.Kassawara,et al.Seismic Fragility Application Guide[R].EPRI 1002988,Electric Power Research Institute(EPRI),Palo Alto,California,2002.
[6]Jack R,et al.A Methodology for Assessment ofNuclear Power Plant Seismic Margin[R].EPRI NP-6041SL,Revision 1,Electric Power Research Institute(EPRI),Palo Alto,california,1991.
[7]SQUG.Generic Implementation Procedure(GIP)forSeismic Verification of Nuclear Plant Equipment Revision 2[S].Corrected,Seismic Qualification utility Group,1991.
[8]SQUG.Procedure for Gathering and ValidatingEarthquake Experience Data,Revision 3[R].SeismicQualification Utility Group,2001.
[9]R.Kennedy,et al.Evaluation of JNES EquipmentFragility Tests for Use in Seismic Probabilistic RiskAssessments for U.S.Nuclear Power Plants[R].NUREG/CR-7040,2011.
[10]M.S.Power,et al.Engineering Characterization ofGround Motion,Task 1:Effects of Characteristics ofFree-Field Motion on Structural Response[R].NUREG/CR-3805,1984.
[11]PG&E.Final Report of the Diablo Canyon Long TermSeismic Program[R].Pacific Gas and ElectricCompany,Docket 50-275and 50-323,1988.
[12]Bohn,M.P.and J.A.Lambright.Procedures for theExternal Event Core Damage Frequency Analyses forNUREG-1150[R].NUREG/CR-4840,1990.
[13]Budnitz,R.J.State-of-the-Art Report on the CurrentStatus of Methodologis for Seismic PSA[R].NEA/SCNI(97)22,Committee on the Safety of NuclearInstallations,OECD Nuclear Neergy Agency,1998.
[14]R.P.Kennedy,et al.Assessment of Seismic MarginCalculation Methods[R].NUREG/CR-5270,LawrenceLivermore National Laboratory and U.S.NuclearRegulatory Commission,1989.
[2]M.P.Bohn,J.A.Lambright,Severe Accident Risk,An Assessment of Five US Nuclear Power Plants[R].NUREG-1150,Volumes 1and 2,1990.
[3]Jack R,et al.Methodlogy for Developing SeismicFragilities[R].EPRI TR-103959,Electric PowerResearch Institute(EPRI),Palo Alto,California,1994.
[4]J.Hickman,et al.PRA Procedures Guide:A Guide tothe Performance of Probabilistic Risk Assessments forNuclear Power Plants[S].NUREG/CR-2300,American Nuclar Society,Institute of Electrical andElectronic Engineers,and U.S.Nuclear RegulatoryCommissin,1983.
[5]R.Kassawara,et al.Seismic Fragility Application Guide[R].EPRI 1002988,Electric Power Research Institute(EPRI),Palo Alto,California,2002.
[6]Jack R,et al.A Methodology for Assessment ofNuclear Power Plant Seismic Margin[R].EPRI NP-6041SL,Revision 1,Electric Power Research Institute(EPRI),Palo Alto,california,1991.
[7]SQUG.Generic Implementation Procedure(GIP)forSeismic Verification of Nuclear Plant Equipment Revision 2[S].Corrected,Seismic Qualification utility Group,1991.
[8]SQUG.Procedure for Gathering and ValidatingEarthquake Experience Data,Revision 3[R].SeismicQualification Utility Group,2001.
[9]R.Kennedy,et al.Evaluation of JNES EquipmentFragility Tests for Use in Seismic Probabilistic RiskAssessments for U.S.Nuclear Power Plants[R].NUREG/CR-7040,2011.
[10]M.S.Power,et al.Engineering Characterization ofGround Motion,Task 1:Effects of Characteristics ofFree-Field Motion on Structural Response[R].NUREG/CR-3805,1984.
[11]PG&E.Final Report of the Diablo Canyon Long TermSeismic Program[R].Pacific Gas and ElectricCompany,Docket 50-275and 50-323,1988.
[12]Bohn,M.P.and J.A.Lambright.Procedures for theExternal Event Core Damage Frequency Analyses forNUREG-1150[R].NUREG/CR-4840,1990.
[13]Budnitz,R.J.State-of-the-Art Report on the CurrentStatus of Methodologis for Seismic PSA[R].NEA/SCNI(97)22,Committee on the Safety of NuclearInstallations,OECD Nuclear Neergy Agency,1998.
[14]R.P.Kennedy,et al.Assessment of Seismic MarginCalculation Methods[R].NUREG/CR-5270,LawrenceLivermore National Laboratory and U.S.NuclearRegulatory Commission,1989.
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