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核电厂和缓环境、显著老化机理与设备鉴定 被引量:10

Mild Environment of Nuclear Power Plants,Significant Aging Mechanism and Equipment Qualification
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摘要 本文论述了安装在核电厂和缓环境中1E级设备老化机理的非显著性及确定鉴定寿命的不必要性,明确了该环境中一般1E级设备的鉴定试验要求。 The paper discusses the significance of aging mechanism for class 1E equipment installed in mild environment of nuclear power plants, and concludes that it is not necessary to establish the qualified life. The qualification requirements are clarified for most of class 1E equipment installed in mild environment.
作者 郎爱国
出处 《核安全》 2006年第3期11-16,共6页 Nuclear Safety
关键词 核电厂 和缓环境 显著老化机理 鉴定寿命 设备鉴定 nuclear power plants mild environment significant aging mechanism qualified life equipment qualification
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参考文献12

  • 1[2]Code of Federal Regulations,Title 10,Part 50.49,Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants,U.S.Federal Register Vol.48,No.15,January 21,1983
  • 2[3]RCC-E,Design and Construction Rules for Electrical Components of Nuclear Islands,AFCEN,October 2002 Edition
  • 3[4]Draft Regulatory Guide DG-1077 Guidelines for Environmental Qualification of Microprocessor-Based Equipment Important to Safety in Nuclear Power Plants,U.S.Nuclear Regulatory Commission,2001
  • 4[5]IEEE323-2003,IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations,U.S.Institute of Electrical and Electronics Engineers
  • 5[6]IEEE627-1980,IEEE Standard for Design Qualification of Safety Systems Equipment Used in Nuclear Power Generating Stations,U.S.Institute of Electrical and Electronics Engineers
  • 6[7]NUREG/CR-3808,Aging-Seismic Correlmion Study on Class 1E Equipment,U.S.Nuclear Regulatory Commission,1984
  • 7[8]EPRI NP-3326,Correlation Between Aging and Seismic Qualification for Nuclear Plant Electrical Components,U.S.Electric Power Research Institute,1983
  • 8[9]EPRI NP-5024,Seismic Ruggedness of Aged Electrical Components,U.S.Electric Power Research Institute,1987
  • 9[10]EPRI TR-107330,Genetic Requirements Specification for Qualifying a Commercially Available PLC for Safety-Related Applications in Nuclear Power Plants,U.S.Electric Power Research Institute,1996
  • 10[11]Safety Evaluation by The Office of Nuclear Reactor Regulation,SIEMENS Power Corporation Topical Report EMF2110(NP),TELEPERM XS:A Digital Reactor Protection System,Project No.702,U.S.Nuclear Regulatory Commission,2000

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