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核电站重要敏感设备加速老化管理研究与应用 被引量:2

Research and application of accelerated ageing management for important and susceptible components in nuclear power plants
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摘要 介绍了大亚湾核电站和岭澳核电站重要敏感设备加速老化管理技术研究的背景,阐述了加速老化管理的内涵,论述了电站加速老化管理技术路线、工作体系,以及同现有运行和维修体系的接口。通过加速老化管理技术的应用实例论证了相关研究成果的合理性和有效性。最后对核电站重要敏感设备加速老化管理技术的发展前景进行了展望。 This paper introduced the background of research on accelerated ageing management (AAM) technology for important and susceptible components in Daya Bay nuclear power plant (NPP) and Lingao NPP, and expounded the connotation of AAM, demonstrated the AAM technical route, work architecture and interfaces with existing operation and maintenance system in NPPs. Some representative application examples of AAM technology for verifying the rationality and effectiveness of relevant research achievements also were presented. Development prospect of AAM technology was proposed at the last.
出处 《核科学与工程》 CSCD 北大核心 2011年第2期185-192,共8页 Nuclear Science and Engineering
关键词 加速老化 加速老化管理 重要敏感设备 核电站 accelerated ageing accelerated ageing management important and susceptible components nuclear power plant
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  • 1IAEA safety standards for protecting people and the environment: Ageing managements for nuclear power ptants[R]. DS382, IAEA, May, 2007.
  • 2IAEA Safety Report Series No. 15: Implementation and review of nuclear power plant ageing management programme[R]. IAEA, 1999.
  • 3IAEA. Safety aspects of nuclear power plant ageing [R]. IAEA-TECDOC-540. 1990.
  • 4IAEA. Pilot study on the management oI ageing of instrumentation and control cables[R]. IAEA-TECDOC- 932. 1997.
  • 5IAEA. Assessment and management of ageing of major nuclear power plant components important to safetY: CANDU reactor assemblies[R]. IAEA-TECDOC-1197, Feb, 2001.
  • 6U. S. NRC. A reliability physics model for aging of cable insulation materials[R]. NUREG/CR-6869, 2005.
  • 7EPRI. 2003 EDF/EPRI Collaboration on Life Cycle Management and Nuclear Asset Management[R]. TR1008947, Dec, 2003.
  • 8戴忠华,刘鹏,卢文跃,陈世均.大亚湾核电站的老化和寿命管理[J].核动力工程,2005,26(S1):87-89. 被引量:9
  • 9Kaisa Simola. Reliability methods in nuclear power plant ageing management[D]. Helsinki University of Teehnology, Finland, May 1999:17.
  • 10陈宇 黄立军 黄卫刚.核电站应急柴油发电机缸头密封水套加速老化分析与管理对策研究.大亚湾核电,2009,12.

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