AP1000抗震分析与设计特点研究
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摘要
对AP1000抗震分析与设计的主要特点进行分析,并将这些特点同现有核电站的设计状况和我国潜在厂址的情况进行对比。研究侧重于抗震分类、抗震设防水准及设计地震、地基岩土条件、抗震裕度分析等几个主要方面。通过研究,把握AP1000抗震分析与设计的主要特点,对其设计特点和适应性加深理解,并提出需要继续跟踪研究和关注的问题。研究成果可以为后续研究和AP1000堆型的工程引进提供参考和基础素材。其中关于抗震裕度分析的研究内容对于在我国开展在役核电厂的地震安全评估和3级PRA分析亦有借鉴意义。
The major features of seismic analysis and design of AP1000 are studied,which are compared with the relatives of an existing nuclear power plant and with actual situation of a potential site in China.The important issues for the seismic design and safety evaluation of a nuclear power plant are emphasized in this article,namely seismic categories,response spectra of design ground motion,soil conditions and seismic margin analysis.As better understanding about the major characteristics of the seismic analysis and design of the nuclear power plant,the preliminary evaluation conclusions on the technical issues and maturity of AP1000 seismic design,and also some suggestions for the successive study and engineering implementation are raised.And the research contents with related to seismic margin analysis of AP1000 would be provided some useful references to the seismic safety evaluation and Level 3 PSA for an existing nuclear power plant.
The major features of seismic analysis and design of AP1000 are studied,which are compared with the relatives of an existing nuclear power plant and with actual situation of a potential site in China.The important issues for the seismic design and safety evaluation of a nuclear power plant are emphasized in this article,namely seismic categories,response spectra of design ground motion,soil conditions and seismic margin analysis.As better understanding about the major characteristics of the seismic analysis and design of the nuclear power plant,the preliminary evaluation conclusions on the technical issues and maturity of AP1000 seismic design,and also some suggestions for the successive study and engineering implementation are raised.And the research contents with related to seismic margin analysis of AP1000 would be provided some useful references to the seismic safety evaluation and Level 3 PSA for an existing nuclear power plant.
引文
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[2]NRC Regulatory Guide 1.29-1978.Seismic Design Classification[S].
[3]姚伟达,张明,秦承军.先进压水反应堆业主要求文件(ALWR-URD)中对核电厂抗震设计要求[J].核安全,2004.3.
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[6]ASCE 4-86,Seismic Analysis of Safety-Related Nuclear Structures and Commentary on Standard for Seismic Analysis of Safety-Related NuclearStructures[S].
[7]Campbell R D,Hardy G S,Ravindra MK,Johnson J J,Hoy AJ.Seismic reevaluation of nuclear facilities worldwide:overviewand status[J].Nuclear Engineering and Design,1998,182(1):17-34.
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[10]Gu¨rpinar A,Godoy A.Seismic safety of nuclear power plants in eastern europe[J].Nuclear Engineering and Design,1998,182(1):47-58.
[11]Oikawa T,Kondo M,Mizuno Y,Watanabe Y,Fukuoka H,Muramatsu K.Development of systems reliability analysis code SECOM-2 for seis-mic PSA[J].Reliability Engineering and System Safety,1998,62(3):251-271.
[2]NRC Regulatory Guide 1.29-1978.Seismic Design Classification[S].
[3]姚伟达,张明,秦承军.先进压水反应堆业主要求文件(ALWR-URD)中对核电厂抗震设计要求[J].核安全,2004.3.
[4]NRC Regulatory Guide 1.60-1973,Design Response Spectra for Seismic Design of Nuclear Power Plants[S].
[5]NRC Standard Review Plan,NUREG-0800[S].1975.
[6]ASCE 4-86,Seismic Analysis of Safety-Related Nuclear Structures and Commentary on Standard for Seismic Analysis of Safety-Related NuclearStructures[S].
[7]Campbell R D,Hardy G S,Ravindra MK,Johnson J J,Hoy AJ.Seismic reevaluation of nuclear facilities worldwide:overviewand status[J].Nuclear Engineering and Design,1998,182(1):17-34.
[8]Chen J T,Connell E,Chokshi N,et al.Preliminary perspectives gained from Individual plant examination of external events(IPEEE)seismic andfire submittal review[J].Nuclear Engineering and Design,1999,181(1):91-104.
[9]Campbell R,Short S,Ravintra M,Hardy G,Johnson J.Seismic reevaluation and upgrading of nuclear power facilities outside the US using USdeveloped methodologies[R].1998,181.115-129.
[10]Gu¨rpinar A,Godoy A.Seismic safety of nuclear power plants in eastern europe[J].Nuclear Engineering and Design,1998,182(1):47-58.
[11]Oikawa T,Kondo M,Mizuno Y,Watanabe Y,Fukuoka H,Muramatsu K.Development of systems reliability analysis code SECOM-2 for seis-mic PSA[J].Reliability Engineering and System Safety,1998,62(3):251-271.
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