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核电厂运行风险管理 被引量:3

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摘要 针对核电厂存在放射性危害风险的事实,总结了大亚湾核电厂生产活动中风险管理的实践,并根据风险管理技术的发展,提出了在核电厂应用风险管理技术提高安全生产业绩的方法。
作者 丁震行
出处 《电力安全技术》 2002年第11期4-6,共3页 Electric Safety Technology
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参考文献6

  • 110 CFR 50.65. Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.
  • 2IAEA-TECDOC-928.Good Practices for Cost Effective Maintenance of Nuclear Power Plants,1997.
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  • 6钱永柏,童节娟,张作义.基于风险指引安全分级的维修规则实施方案[J].核动力工程,2007,28(5):75-78. 被引量:9

二级参考文献9

  • 1景建国,戴忠华.状态检修在核电站设备管理中的作用[J].中国电力,2004,37(8):31-34. 被引量:4
  • 2USNRC 10 CFR 50.65. Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants[S]. 2003.
  • 3Regulatory Guide 1.160 (Rev.2). Monitoring the Effectiveness of Maintenance at Nuclear Power Plants[S].1997.
  • 4NUMARC 93-01(Revision 3). Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants[S]. 2000.
  • 5USNRC 10 CFR 50.69. Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (Final rule)[S]. 2004.
  • 6HAF103-2004.核动力厂运行安全规定[S].
  • 7Grantom C R (Rick). PSA Techniques in Component Risk Significance Categorization for Graded Quality Assurance and Exemption from Special Treatment Requirement (risk informed part 50, option2). International Workshop on “Use of PSA in Operation of NPPs and in Regulatory Decision-Making”. May 19, 2004. Kyiv, Ukraine.
  • 8丁震行.核电厂运行风险管理[J].电力安全技术,2002,4(11):4-6. 被引量:3
  • 9朱树中.美国核电厂风险评估的安全效益(三)[J].国外核新闻,2003(4):25-28. 被引量:2

共引文献8

同被引文献15

  • 1张善明.大亚湾核电站减少非计划停堆停机策略与实践[J].核科学与工程,2001,21(S1):7-12. 被引量:1
  • 2景建国,戴忠华.状态检修在核电站设备管理中的作用[J].中国电力,2004,37(8):31-34. 被引量:4
  • 3高亚娟.风险控制与安全管理[J].东北电力技术,2005,26(2):43-44. 被引量:6
  • 4黄世强.风险控制与核电安全[J].中国电力,2005,38(5):69-72. 被引量:1
  • 5USNRC 10 CFR 50.65. Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants[S]. 2003.
  • 6Regulatory Guide 1.160 (Rev.2). Monitoring the Effectiveness of Maintenance at Nuclear Power Plants[S].1997.
  • 7NUMARC 93-01(Revision 3). Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants[S]. 2000.
  • 8USNRC 10 CFR 50.69. Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (Final rule)[S]. 2004.
  • 9HAF103-2004.核动力厂运行安全规定[S].
  • 10Grantom C R (Rick). PSA Techniques in Component Risk Significance Categorization for Graded Quality Assurance and Exemption from Special Treatment Requirement (risk informed part 50, option2). International Workshop on “Use of PSA in Operation of NPPs and in Regulatory Decision-Making”. May 19, 2004. Kyiv, Ukraine.

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