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压水堆核电站疲劳监测系统分析 被引量:12

Analysis of Fatigue Monitoring Systems in PWR Nuclear Power Plants
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摘要 核电站反应堆冷却管道疲劳问题是核电站老化管理关注重点之一,特别是当核电站服役年限渐长、定期安全审查(PSR)、电站申请延寿时,核监管机构要求核电站必须提供相关的信息以验证疲劳对部件的损伤影响程度。通过对目前核电站疲劳监测系统的调研,分析了主流疲劳监测系统的功能、相关的参数及彼此间的差异性。 The fatigue problem for primary circuit of nuclear power plants (NPPs) is one of the key focus on aging management, especially when nuclear power plant's service life grows, or the nuclear regulators require nuclear power plants to provide relevant information to verify the fatigue damage of components when the NPPs apply periodic safety review (PSR) and life extension. In this paper, an investigation on the fatigue monitoring systems was carried out, and the fatigue monitoring system functions and parameters related to the differences between each other were com-pared, in order to provide information for the selection or independent research and development of the monitoring system for NPPs in the future.
出处 《华东电力》 北大核心 2013年第11期2398-2403,共6页 East China Electric Power
基金 国家科技重大专项(2011ZX06004-002-03)~~
关键词 核电站 疲劳监测 热瞬态 nuclear power plant fatigue monitoring thermal transient
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参考文献11

  • 1PACHNER J. Assessment and management of ageing of major nuclear power plan! components important to safety Primary piping in PWRs[ R]. IAEA TECDOC-1361, 2003.
  • 2CAREY J. Operating experience regarding thermal fatigue of unisolable piping connected to PWR reactor coolant systems [ R]. EPRI Report No. 1001006, 2000,.
  • 3NRC Bulletin 79-13, Revision 2, Cracking in Feedwater Sys- tem Piping[ N]. June 1979.
  • 4BIMONT G, AUFORT P. Fatigue Monitoring in Nuclear Power' Plant [ C ]. Transactions of the 9th, International Con- ference on SMiRT, Lausanne, Switzerland, August, 1987, 133-140.
  • 5NRC Bulletin 88-08, Thermal Stresses in Piping Connected to Reactor Coolant Systems[ N ]. April 11, 1989.
  • 6NRC Bulletin 88-11, Pressurizer Surge l.ine Thermal Stratifi- cation[ N]. December 10, 1988.
  • 7GR1ESBACH T J. FatiguePro: An On-Line Fatigue Usage Transient Monitoring System tbr Nuclear Power Plants [ R ]. EPRI Report No. NP-5835. 1988.
  • 8MIKSCH M, SCHON G, THOMAS B. FAMOS- a tool for transient tecnrding and fatigue monitoring [ C ]. ASME Pres- sure Vessels and Piping Conference, PiUsburgh, Pennsylva- nia, June 19-23, 1988, pp. 27-34.
  • 9KLEINODER W, POCKI. C. Developing and hnplementation of a thtigue monitoring system for the new Earopean pressur- ized water reactor EPR [ C ]. Proceedings of the International Conference " Nuclear Energy tor New Europe 2007". Porto- roz, 10-13 September, 2007.
  • 10BOGACHEV A V, DRANCHENKO B N, SEM1SHKIN V P. Development of system SACOR-M[C]. Issues of nuclear sci- ence and engineering. Series NPP safety assurance. Scientific and technical collection. Issue 15. WWER reactor plants. Podolsk. 2006.

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