核电厂结构地震响应分析的时频域分析方法比较
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摘要
进行核电厂安全相关结构的抗震分析时,中国和美国规范推荐的计算方法有所不同,中国核电厂抗震设计规范(GB50267-97)中推荐时程法(时域法),而美国土木工程师学会的安全相关的核电结构的抗震分析(ASCE4-98)则建议时域法和频域法,因此这两种方法的比较对了解核电厂地震动力响应有重要意义.本文基于同一个典型的核岛结构,分别采用时域法和频域法计算核电厂的地震响应.计算结果表明,时域法和频域法得到较为一致的结构峰值加速度和反应谱.由于频域法用于核电厂地基—结构分析方便性和计算结果的稳定性,建议中国核电厂抗震设计规范增加频域分析方法.
The methods for the seismic analysis of safety-related nuclear structures are difference in the codes between China and US.The Chinese code for seismic design of nuclear power plant(GB50267-97)provides the time history method,while seismic analysis of safety-related nuclear structures and commentary of American Society of Civil Engineers(ASCE4-98)recommends methods of both time history(time domain)and the analysis of complex frequency response(frequency domain).Therefore,a comparision of these two methods is essential for deep understanding of seismic responses of the nudear power plants.Based on the typical structure of a nuclear island,we calculated the seismic response of nuclear power plants by using these two methods.The calculation results clearly show that the agreement in the peak acceleration and spectral accelerations of structural responses.Since the complex frequency response method is particularly suitable for the soil-structure isteraction analysis of nuclear power plants.It is recommended that the Chinese nuclear safety code shold added the frequency domain method for the seismic design of nuclear power plants.
The methods for the seismic analysis of safety-related nuclear structures are difference in the codes between China and US.The Chinese code for seismic design of nuclear power plant(GB50267-97)provides the time history method,while seismic analysis of safety-related nuclear structures and commentary of American Society of Civil Engineers(ASCE4-98)recommends methods of both time history(time domain)and the analysis of complex frequency response(frequency domain).Therefore,a comparision of these two methods is essential for deep understanding of seismic responses of the nudear power plants.Based on the typical structure of a nuclear island,we calculated the seismic response of nuclear power plants by using these two methods.The calculation results clearly show that the agreement in the peak acceleration and spectral accelerations of structural responses.Since the complex frequency response method is particularly suitable for the soil-structure isteraction analysis of nuclear power plants.It is recommended that the Chinese nuclear safety code shold added the frequency domain method for the seismic design of nuclear power plants.
引文
[1]中华人民共和国国家标准.核电厂抗震设计规范[S].GB/50267-97,1997State Standard of the People’s Repubic of China.Code for seismic design of nuclear power plants[S〗。GB/50267-97,1997
[2]ASCE 4-98 Standard.Seismic analysis of safety-related nuclear structures and commentary.American Society of CivilEngineers,2000
[3]Finite element modeling of the AP1000 nuclear island for seismic analysis at generic soil and rock sites[R].Beijing:SMiRT18-J12-1,2005
[4]AP1000 Design Control Document Rev.17[G].2009
[5]U.S.Nuclear Regulatory Commission NUREG-0800,Standard Review Plan,Section3.7.1[L].Seismic Input Rev.3(2007)
[6]U.S.Nuclear Regulatory Commission,Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components[L].RG1.122 Rev.1 Washington,D.C.USA,(1978)
[7]U.S.Nuclear Regulatory Commission NUREG-0800,Standard Review Plan,Section3.7.4[L].Seismic System AnalysisRev.3(2007)
[2]ASCE 4-98 Standard.Seismic analysis of safety-related nuclear structures and commentary.American Society of CivilEngineers,2000
[3]Finite element modeling of the AP1000 nuclear island for seismic analysis at generic soil and rock sites[R].Beijing:SMiRT18-J12-1,2005
[4]AP1000 Design Control Document Rev.17[G].2009
[5]U.S.Nuclear Regulatory Commission NUREG-0800,Standard Review Plan,Section3.7.1[L].Seismic Input Rev.3(2007)
[6]U.S.Nuclear Regulatory Commission,Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components[L].RG1.122 Rev.1 Washington,D.C.USA,(1978)
[7]U.S.Nuclear Regulatory Commission NUREG-0800,Standard Review Plan,Section3.7.4[L].Seismic System AnalysisRev.3(2007)
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