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浅析乏燃料水池冷却和处理系统(PTR)的设计改进 被引量:4

Analysis of the Design Improvement of Spent Fuel Pool Cooling System
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摘要 讨论了乏燃料水池冷却和处理系统设计改进的原因、设计要求和可行性,得出了改进应遵循的基本原则。 The ments and feasibility on are obtained. design improvement are discussed in this of spent fuel pool cooling system in facets paper, and the basic principle, the design of reasons, require- improvement basing
出处 《核安全》 2012年第2期72-75,共4页 Nuclear Safety
关键词 PTR系统 设计改进 分析 PTR design improvement analysis
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参考文献2

  • 1中国核工业总公司.压水堆核电厂燃料装卸和贮存系统设计准则[S],1992.
  • 2国防科学技术工业委员会.压水堆核电厂乏燃料贮存设施设计准则[S],2006.

同被引文献29

  • 1李灿,凌星.核电站乏燃料贮存水池失去最终热阱时的安全分析[J].核动力工程,2006,27(5):70-73. 被引量:9
  • 2韩宝华.放射性去污废液中的有机物及其处理技术[J].辐射防护通讯,2007,27(1):36-41. 被引量:5
  • 3Fukushima Nuclear Accident Independent Investigation Commission. Investigation Committee on the Accident at Fukushima Nuclear Power Stations of Tokyo Electric Power Company,Interim Report[R].Tokyo:Fukushima Nuclear Accident Independent Investigation Commission,2011.
  • 4Fukushima Nuclear Accident Independent Investigation Commission. Investigation Committee on the Accident at Fukushima Nuclear Power Stations of Tokyo Electric Power Company,Final Report[R].Tokyo:Fukushima Nuclear Accident Independent Investigation Commission,2012.
  • 5IAEA. Safety of Nuclear Power Plants:Design[S].Vienna:IAEA,2012.
  • 6林诚格.非能动安全先进核电厂AP1000[M]北京:原子能出版社,2008.
  • 7Atomic Energy Society of Japan. Lessons learned from the accident at the Fukushima Daiichi Nuclear Power Plant[R].Tokyo:Atomic Energy Society of Japan,2011.
  • 8DOE. Nuclear Energy Research Advisory Committee.Forum,G.I.I.A Technology Roadmap for Generation Ⅳ Nuclear Energy System[M].Oak Ridge:DOE,2002.
  • 9韩旭,郑明光,杨燕华.广义非能动系统概念研究[J].核动力工程,2009,30(3):115-118. 被引量:6
  • 10刘昱,刘佩,张明乾.压水堆核电站废液处理系统的比较[J].辐射防护,2010,30(1):42-47. 被引量:17

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