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稳压器波动管热分层分析 被引量:14

Thermal Stratification Study for Pressurizer Surge Line
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摘要 为评价热分层对稳压器波动管结构完整性的影响,从理论上分析了稳压器波动管热分层发生的条件。以百万千瓦级三环路压水堆核电厂核反应堆启堆为例,建立了热分层瞬态,研究了热分层应力计算方法,从理论上将一个复杂的三维应力分析问题简化为一维和二维组合问题。结合ANSYS程序功能,提出了波动管热分层应力计算的工程方法。 In order to confirm the structural integrity of pressurizer surge line affected by thermal stratification, this paper theoretically analyzes the criterion of thermal stratified occurrence, establishes the thermal stratified transient by start-up of reactor, and studies the calculation method of thermal stratified stress. A complex 3-dimension problem is simplified into a combined one of 1-dimension and 2-dimension. Considering ANSYS code function, an engineering method is put forward for thermal stratified stress calculation of pressurizer surge line.
作者 张毅雄 杨宇
出处 《核动力工程》 EI CAS CSCD 北大核心 2006年第6期13-17,共5页 Nuclear Power Engineering
基金 中国核动力研究设计院青年基金
关键词 稳压器波动管 热分层 应力分析 Pressurizer surge line, Thermal stratification, Stress analysis
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参考文献6

  • 1NRC Bulletin 88-08,1988.Thermal Stresses in Piping Connected to Reactor Coolant Systems.US NRC.
  • 2NRC Bulletin 88-11,1988.Pressurizer Surge Line Thermal Stratification.US NRC.
  • 3Y.J.Yu,S.H.Park,G.H.Sohn.Structural Evaluation of Thermal Stratification for PWR Surge Line[J].Nuclear Engineering and Design,1997,178:221 ~ 220.
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同被引文献89

  • 1李澍,曹小伟.压水堆稳压器波动管热分层的分析研究[J].核动力工程,2009,30(S2):31-34. 被引量:5
  • 2谭璞,李剑波.核电厂管道热疲劳机理与防治[J].核安全,2011,10(4):23-28. 被引量:16
  • 3Yu Y J, Park S H, Sohn G H. Structural Evaluation of Thermal Stratification for PWR Surge Line[J]. Nuclear Engineering and Design, 1997, 178: 211-220.
  • 4US NRC.NRC Bulletin 88-08, Thermal Stresses in Piping Connected to Reactor Coolant Systems[S]. 1988.
  • 5US NRC. NRC Bulletin 88-11, Pressurizer Surge Line Thermal Stratification[S]. 1988.
  • 6Ensel C, Colas A, Barthez M. Stress Analysis of a 900MW Pressurizer Surge Line Including Stratification Effects[J]. Nuclear Engineering and Design, 1995, 153: 197-203.
  • 7(德)海恩慈·赫尔威格.传热词汇A-Z,基本概念与详尽诠释[M].彭晓峰,张扬译.北京:机械工业出版社,2007.
  • 8于勇.FLUENT入门与进阶教程[M].北京:北京理工大学出版社,2008.
  • 9AFCEN.RCC-M规范[S].2000版加2002补遗.
  • 10NRC Bulletin 88-08. Thermal Stresses in Piping Connected to Reactor Coolant Systems [S].

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