福岛核事故后中国广东核电集团核电厂抗震设计和评估进展
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摘要
本文介绍了核电站抗震设计要求、在建和运行核电站的抗震设计情况以及运行核电站遭遇地震灾害的情况,简述了福岛核事故后世界各国核电站在抗震方面采取的措施,针对中国广东核电集团在福岛核事故后的行动进行了详细介绍,并提出了新建核电厂在抗震设计和评估方面的策略,以期通过技术手段持续提升核电站的抗震能力。
This paper introduced the seismic design requirements of nuclear power plant,the seismic design situation of the unit in construction or in service,and the serious consequence impacted by earthquake.Then,it described in brief the measures on seismic analysis taken by countries who own nuclear power plants in the world after the Fukushima nuclear accident,and gave a particular introduction about the improvement taken by China Guangdong Nuclear Power Holding Co.Ltd.Finally,this paper presented some steps for the new nuclear power plants at the seismic design and evaluation to enhance the seismic capacity of nuclear power plants through technical means.
This paper introduced the seismic design requirements of nuclear power plant,the seismic design situation of the unit in construction or in service,and the serious consequence impacted by earthquake.Then,it described in brief the measures on seismic analysis taken by countries who own nuclear power plants in the world after the Fukushima nuclear accident,and gave a particular introduction about the improvement taken by China Guangdong Nuclear Power Holding Co.Ltd.Finally,this paper presented some steps for the new nuclear power plants at the seismic design and evaluation to enhance the seismic capacity of nuclear power plants through technical means.
引文
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[7]姚伟达,张明,秦承军.先进轻水反应堆业主要求文件(AL-WR—URD)中对核电厂抗震设计要求[J].核安全,2004(3):26-31.
[8]U.S.NRC.SECY-93-087Policy,technical,and licensing issues pertaining to evolutionary and advanced light-water reactor(AL-WR)designs[S].U.S.:Nuclear Regulatory Commission,1993.
[9]James M T.Elimination of operating-basis earthquake policy is-sue,NRC-SECY-93-087[R].U.S.:Nuclear Regulatory Commis-sion,1993.
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[11]ASME.Code Case N-411-1ASME boiler and pressure vessel code[S].New York:American Society of Mechanical Engi-neers,1986.
[12]U.S.NRC.RG1.61Damping values for seismic design of nuclear power plants[S].U.S.:Nuclear Regulatory Commission,2007.
[13]法国核岛设备设计、建造及在役检查规则协会.RCC-M压水堆核岛机械设备设计和建造规则(1993版)[M].核工业第二研究设计院译.北京:核工业第二研究设计院,1996.
[14]法国核岛设备设计、建造及在役检查规则协会.RCC-M压水堆核岛机械设备设计和建造规则(2000版+2002补遗)[M].中科华核电技术研究院有限公司译.上海:上海科学技术文献出版社,2010.
[15]国家地震局.GB502672—97核电厂抗震设计规范[S].北京:中国计划出版社,1997.
[16]潘蓉.日本柏崎.刈羽核电厂新潟地震震害经验[J].核安全,2008(1):20-23.
[2]国家核安全局,国家地震局.HAD101/01核电厂厂址选择中的地震问题[S].北京:中国法制出版社,1994.
[3]国家核安全局.HAD102/02核电厂的抗震设计与鉴定[S].北京:中国法制出版社,1996.
[4]EPRI.ALWR-URD,advanced light water reactor utility require-ments document[S].U.S.:Electric Power Research Institute,1995.
[5]EUR.European utility requirements for LWR nuclear power plants,1955DTN(Revision B)[S].France:Electricity de France,1995.
[6]U.S.NUREG-0800Standard review plan for the review of safety analysis reports for nuclear power plants[S].U.S.:Nuclear Regu-latory Commission,2007.
[7]姚伟达,张明,秦承军.先进轻水反应堆业主要求文件(AL-WR—URD)中对核电厂抗震设计要求[J].核安全,2004(3):26-31.
[8]U.S.NRC.SECY-93-087Policy,technical,and licensing issues pertaining to evolutionary and advanced light-water reactor(AL-WR)designs[S].U.S.:Nuclear Regulatory Commission,1993.
[9]James M T.Elimination of operating-basis earthquake policy is-sue,NRC-SECY-93-087[R].U.S.:Nuclear Regulatory Commis-sion,1993.
[10]U.S.NRC.RG1.61Damping values for seismic design of nuclear power plants[S].U.S.:Nuclear Regulatory Commission,1973.
[11]ASME.Code Case N-411-1ASME boiler and pressure vessel code[S].New York:American Society of Mechanical Engi-neers,1986.
[12]U.S.NRC.RG1.61Damping values for seismic design of nuclear power plants[S].U.S.:Nuclear Regulatory Commission,2007.
[13]法国核岛设备设计、建造及在役检查规则协会.RCC-M压水堆核岛机械设备设计和建造规则(1993版)[M].核工业第二研究设计院译.北京:核工业第二研究设计院,1996.
[14]法国核岛设备设计、建造及在役检查规则协会.RCC-M压水堆核岛机械设备设计和建造规则(2000版+2002补遗)[M].中科华核电技术研究院有限公司译.上海:上海科学技术文献出版社,2010.
[15]国家地震局.GB502672—97核电厂抗震设计规范[S].北京:中国计划出版社,1997.
[16]潘蓉.日本柏崎.刈羽核电厂新潟地震震害经验[J].核安全,2008(1):20-23.
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