中国核电工程场地设计地震动参数确定相关问题
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摘要
基于中国核电工程选址和建设的实际工作,探讨了核电工程场地设计地震动参数确定几个环节中的关键问题,包括不同地震危险性分析方法的采用、地震动衰减关系的选取和设计地震动参数的综合取值等。分析了地震动衰减关系不确定性和弥散地震衰减关系等问题处理方式的变迁,比较分析了地震危险性分析确定性方法中构造地震、弥散地震的计算结果和概率方法计算结果的差异及对设计地震动参数确定的控制作用。研究表明:a.综合考虑地震危险性分析的确定性方法和概率方法的计算结果已成为中国核电工程场地地震安全性评价中确定设计地震动参数的基本思路,其中弥散地震是一个需要特殊考虑的问题;b.确定性方法和概率方法计算结果对场地设计地震动参数的控制作用受区域地震活动性强弱的影响;c.在地震活动性较弱的地区,确定性方法特别是弥散地震计算结果基本上控制着场地设计地震动参数的取值,而在地震活动性相对较强的地区,更倾向于由概率方法计算结果控制。
Based on the recent practical work of evaluation of seismic safety for the nuclear power plant site selection and construction in China,some key issues were discussed involved in the determination of site specific design ground motion for nuclear power plants,including the seismic hazard analysis methods,the ground motion attenuation relations,and the methods of determining design ground motion parameter.The countermeasure change was analyzed to consider the uncertainty of ground motion attenuation relation and the ground motion attenuation relation of diffuse earthquake;the differences were discussed between the computed results from the probabilistic method and the approaches of the diffuse earthquakes and tectonic earthquakes in the deterministic method,and their controlling effects were also discussed on the determination of site specific design ground motion.The results indicated that:a.comprehensive consideration of seismic hazard analysis results from the deterministic method and probabilistic method is the basic ideas of determining design ground motion parameters in the evaluation of seismic safety for nuclear power plant sites,in which the diffuse earthquake is a special problem considered;b.the controlling effects of the computed results from the probabilistic method and deterministic method on the determination of site specific design ground motion are affected by the seismicity in the study area;c.in the weaker seismicity areas,site specific design ground motion parameters are mostly controlled by the computed results from the deterministic method,especially from the approach of diffuse earthquake,but in relatively strong seismicity areas,site specific design ground motion parameters are more likely controlled by the computed results from the probabilistic method.
Based on the recent practical work of evaluation of seismic safety for the nuclear power plant site selection and construction in China,some key issues were discussed involved in the determination of site specific design ground motion for nuclear power plants,including the seismic hazard analysis methods,the ground motion attenuation relations,and the methods of determining design ground motion parameter.The countermeasure change was analyzed to consider the uncertainty of ground motion attenuation relation and the ground motion attenuation relation of diffuse earthquake;the differences were discussed between the computed results from the probabilistic method and the approaches of the diffuse earthquakes and tectonic earthquakes in the deterministic method,and their controlling effects were also discussed on the determination of site specific design ground motion.The results indicated that:a.comprehensive consideration of seismic hazard analysis results from the deterministic method and probabilistic method is the basic ideas of determining design ground motion parameters in the evaluation of seismic safety for nuclear power plant sites,in which the diffuse earthquake is a special problem considered;b.the controlling effects of the computed results from the probabilistic method and deterministic method on the determination of site specific design ground motion are affected by the seismicity in the study area;c.in the weaker seismicity areas,site specific design ground motion parameters are mostly controlled by the computed results from the deterministic method,especially from the approach of diffuse earthquake,but in relatively strong seismicity areas,site specific design ground motion parameters are more likely controlled by the computed results from the probabilistic method.
引文
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[3]电力工业部,国家地震局,中国核工业总公司.核电厂工程建设项目可行性研究地震工作内容与深度规定(试行)(电计【1995】641号)[S].北京:电力工业部,1995.
[4]中国地震局地球物理研究所,中国地震局地质研究所,中国地震局地壳应力研究所.GB17741—2005工程场地地震安全性评价[S].北京:中国标准出版社,2005.
[5]United States Nuclear Regulatory Commission.Regulatory Guide1.60design response spectra for seismic design of nuclear power plants[S].Vienna:IAEA,1973.
[6]United States Nuclear Regulatory Commission.Regulatory Guide1.165identification and characterization of seismic sourc-es and determination of safe shutdown earthquake ground motion[S].Vienna:IAEA,1997.
[7]International Atomic Energy Agency.Safety Guide No.NS-G-3.3evaluation of seismic hazards for nuclear power plants[S].Vi-enna:IAEA,2002.
[8]International Atomic Energy Agency.Safety Series No.50-SG-S1 earthquake and associated topics in relation to nuclear power-plant siting[S].Vienna:IAEA,1991.
[9]时振梁,环文林,张裕明,等.核电厂地震安全性评价中的地震构造研究[M].北京:中国电力出版社,2004.
[10]常向东.弥散地震评价的原则与方法研究[J].中国地震,2000,16(2):107-113.
[11]中国地震局地球物理研究所.山东海阳核电厂厂址地震安全性评价报告[R].北京:中国地震局地球物理研究所,1998.
[12]李小军,阎秀杰,潘华.中小震近场地震动估计中地震动衰减关系的适用性分析[J].地震工程与工程振动,2005,25(1):1-7.
[13]胡聿贤,周克森,阎秀杰.缺乏地震动加速度记录地区地震动估计的映射法[J].地震工程与工程振动,1996,16(3):1-10.
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