核设备抗震鉴定试验中的功率谱密度问题
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摘要
国家核安全局于1995年发布了《核设备抗震鉴定试验指南》(HAF·J 0053),对我国核设备抗震鉴定工作起到了很好的指导作用。《指南》的"多频波法"要求"由每个人工加速度时程计算出的在频率0.3Hz至24Hz范围内的功率谱密度(PSD)曲线必须包络由要求反应谱计算出的对应频率范围的功率谱密度80%的曲线"。但如何根据"要求反应谱"推导出具有合理保守性的可接受的"功率谱密度"是至今尚未解决的问题,这给核安全监管工作带来很大困惑。本文首先从编制《指南》的主要参考蓝本入手,分析了功率谱密度要求的意义及必要性;然后从反应谱和功率谱密度的定义和计算方法着手,结合"合理保守性"的监管原则,探讨从"要求反应谱"推导"最低可接受功率谱密度"的方法;最后,对我国今后相关的规范标准制定和修订工作以及核安全监管工作提出建议。
In 1995 National Nuclear Safety Administration issued " The Guidelines on Nuclear Equipment Seismic Qualification Tests"(HAF·J 0053),which plays a positive role in regulating our activities on nuclear equipment seismic qualification.The portion of "multifrequency excitations" in "The Guidelines" requires that "the PSD curve calculated from every acceleration time history must envelop the curve of 80%PSD calculated from the required response spectrum in the frequency range of 0.3 Hz to 24 Hz." But,how to deduce the acceptable PSD that is reasonably conservative according to the "required response spectrum" remains an unresolved issue,which in turn brings much trouble into the nuclear regulatory activities.First,this paper starts from the mainly referenced base document for compiling "The Guidelines" to analyze the implications and necessity of the PSD requirement.Then, the method is explored to deduce the "minimum acceptable PSD" from the "required response spectrum" based on the definitions and calculation equations of response spectrum and PSD,taking into consideration the regulatory principle of "reasonably conservative".And lastly,recommendations are put forward on our future works for standards or norms compilation and for nuclear safety supervisions.
In 1995 National Nuclear Safety Administration issued " The Guidelines on Nuclear Equipment Seismic Qualification Tests"(HAF·J 0053),which plays a positive role in regulating our activities on nuclear equipment seismic qualification.The portion of "multifrequency excitations" in "The Guidelines" requires that "the PSD curve calculated from every acceleration time history must envelop the curve of 80%PSD calculated from the required response spectrum in the frequency range of 0.3 Hz to 24 Hz." But,how to deduce the acceptable PSD that is reasonably conservative according to the "required response spectrum" remains an unresolved issue,which in turn brings much trouble into the nuclear regulatory activities.First,this paper starts from the mainly referenced base document for compiling "The Guidelines" to analyze the implications and necessity of the PSD requirement.Then, the method is explored to deduce the "minimum acceptable PSD" from the "required response spectrum" based on the definitions and calculation equations of response spectrum and PSD,taking into consideration the regulatory principle of "reasonably conservative".And lastly,recommendations are put forward on our future works for standards or norms compilation and for nuclear safety supervisions.
引文
[1]国家核安全局.核动力厂设计安全规定,HAF102.2004.
[2]国家核安全局.核电厂抗震设计与鉴定,HAD102/02.1996.
[3]国家核安全局.核设备抗震鉴定试验指南,HAF·J 0053.1995.
[4]国家技术监督局.核电厂安全系统电气设备抗震鉴定.1992.
[5]The American Society of Mechanical Engineers.Qualification of Active Mechanical Equipment Used in Nuclear Power Plant.2007.
[6]International Electrotechnical Commission.Recommended Practices for Seismic Qualification of Electrical Equipment of the Safety System for Nuclear Generating Stations.1998.
[7]The Institute of Electrical and Electronics Engineers.IEEE Recom- ??mended Practice for Seismic Qualification.2004.
[8]江近仁,洪峰.功率谱与反应谱的转换和人造地震波.地震工程与工程震动,1984,4(3):1-11.
[9]U.S.NRC.Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants;LWR Edition,NUREG 0800.1989.
[10]U.S.NRC.Design Response Spectra for Seismic Design of Nuclear Power Plants,RG 1.60.Rev.1.1973.
[11]U.S.NRC.Recommendations for Resolution of Public Comments on USI A-40('Seismic Design Criteria' ),NUREG/CR-5347.1989.
[12]U.S.NRC.Resolution of Generic Safety Issues(Formerly Entitled "A Prioritization of Generic Safety Issues"),NUREG-0933.2010.
[2]国家核安全局.核电厂抗震设计与鉴定,HAD102/02.1996.
[3]国家核安全局.核设备抗震鉴定试验指南,HAF·J 0053.1995.
[4]国家技术监督局.核电厂安全系统电气设备抗震鉴定.1992.
[5]The American Society of Mechanical Engineers.Qualification of Active Mechanical Equipment Used in Nuclear Power Plant.2007.
[6]International Electrotechnical Commission.Recommended Practices for Seismic Qualification of Electrical Equipment of the Safety System for Nuclear Generating Stations.1998.
[7]The Institute of Electrical and Electronics Engineers.IEEE Recom- ??mended Practice for Seismic Qualification.2004.
[8]江近仁,洪峰.功率谱与反应谱的转换和人造地震波.地震工程与工程震动,1984,4(3):1-11.
[9]U.S.NRC.Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants;LWR Edition,NUREG 0800.1989.
[10]U.S.NRC.Design Response Spectra for Seismic Design of Nuclear Power Plants,RG 1.60.Rev.1.1973.
[11]U.S.NRC.Recommendations for Resolution of Public Comments on USI A-40('Seismic Design Criteria' ),NUREG/CR-5347.1989.
[12]U.S.NRC.Resolution of Generic Safety Issues(Formerly Entitled "A Prioritization of Generic Safety Issues"),NUREG-0933.2010.
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