核电厂构筑物和设备高置信度低失效概率抗震能力值的计算方法
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摘要
计算核电厂构筑物、系统和部件(SSC)的高置信度低失效概率抗震能力值(HCLPF)是地震概率安全评价(SPSA)、地震裕度评价(SMA)的一个重要步骤。介绍在工程上常用的3种计算SSC HCLPF值的方法:概率易损性方法、保守的确定性失效裕度(CDFM)方法以及通过试验数据获取HCLPF值的方法,并对比研究近年来在计算HCLPF值方法上的新进展,最后给出了计算HCLPF值的一些建议。
Calculation of the HCLPF value of structure,system and component(SSC) in nuclear power plants(NPPs) is an important process for seismic probability safety assessment(SPSA) and seismic margin assessment(SMA).In this paper,three methods for calculation of the HCLPF value of SSC are presented,such as fragility analysis,conservative deterministic failure margin(CDFM),and HCLPF value based on test.The recent progresses in calculation of the HCLPF value of SSC are investigated.Finally some suggestions for the calculation of the HCLPF value of SSC are proposed.
引文
[1]Kennedy R P.Methodology for Deriving SeismicFragilities[R].Electric Power Research Institute,TR-103959,Palo Alto,California,1994.
    [2]Kassawara R.Seismic Fragilitiy Application Guide[R].Electric Power Research Institute,1003121,Palo Alto,CA:2002.
    [3]Kassawara R.Seismic Fragilitiy Application GuideUpdate[R].Electric Power Research Institute,1019200,Palo Alto,CA:2009.
    [4]Kennedy R P,Ravindra M K.Seismic Fragilities forNuclear Power Plant Risk Studies[J].NuclearEngineering and Design,1984,79:47-68.
    [5]Kennedy R P,Cornell C A,Campbell R D,et.al.Probabilistic Seismic Safety Study of An ExistingNuclear Power Plant[J].Nuclear Engineering andDesign,1980,59:315-338.
    [6]Ajai S,Pisharady1,Prabir C.Basu.Methods to DeriveSeismic Fragility of NPP Components:A Summary[J].Nuclear Engineering and Design,2010,240:3878-3887.
    [7]Kennedy R P.A Methodology for Assessment of NuclearPower Plant Seismic Margin[R].Electric PowerResearch Institute,NP-6041-SL,Palo Alto,California,1991.
    [8]Electric Power Research Institute.Generic SeismicRuggedness of Power Plant Equipment in Nuclear PowerPlants[R].EPRI NP-5223,Palo Alto,California,1991.
    [9]Electric Power Research Institute.Seismic Ruggednessof Relays[R].EPRI NP-7147,Palo Alto,California,1991.
    [10]Kapilesh Bhargava,Ghosh A K,Agrawal M K,et.al.Evaluation of Seismic Fragility of Structures—a CaseStudy[J].Nuclear Engineering and Design,2002,212:253-272.
    [11]Yuichi Watanabe,Ken Muramatsu,Tetsukuni Oikawa.Seismic Capacity Evaluation of A Group of VerticalU-Tube Heat Exchanger with Support Frames forSeismic PSA[J].Nuclear Engineering and Design,2005,235:2495-2512.
    [12]Naohiro Nakamura,Shodo Akita,Takuya Suzuki,et.al.Study of Ultimate Seismic Response and FragilityEvaluation of Nuclear Power Building using NonlinearThree-Dimensional Finite Element Model[J].NuclearEngineering and Design,2010,240:166-180.
    [13]Jung Han Kim,In-Kil Choi,Jin-Hee Park.UncertaintyAnalysis of System Fragility for Seismic SafetyEvaluation of NPP[J].Nuclear Engineering andDesign,2011,241:2570-2579.
    [14]Yin-Nan Huang,Andrew S,Whittaker,et al.AProbabilistic Seismic Risk Assessment Procedure forNuclear Power Plants:(I)Methodology,(II)application[J].Nuclear Engineering and Design,2011,241:3985-4003.

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