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针对热分层现象的稳压器波动管结构评价方法研究及分析程序应用开发 被引量:1

Structural Evaluation Method Study and Procedure Development for Pressurizer Surge Line Subjected to Thermal Stratification Phenomenon
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摘要 稳压器波动管热分层现象对核电厂安全运行具有潜在威胁。根据热分层发生机理,采用Fr数来判断热分层现象是否发生,研究热交换系数的计算方法,并将热分层引起的三维热应力解耦成一维总体应力和二维局部应力。根据RCC-M规范的要求,采用一维和二维组合的应力计算方法,将热分层产生的应力和其他载荷产生的应力叠加,进行结构完整性评定。配套本文提出的分析评价方法,对SYSTUS程序和ROCOCO程序进行应用开发。采用本文的分析评价方法和配套的分析程序,对秦山二期扩建工程稳压器波动管热分层进行分析评价,结果表明:稳压器波动管在热分层效应下结构完整性仍然满足RCC-M规范要求。 Thermal stratification phenomenon of pressurizer surge line can lead potential threaten to plant safety. Base on the mechanism of thermal stratification occurrence, Fr number is used to judge whether the stratification occurs or not. Also the method of calculating heat transfer coefficient is investigated. Theoretically the 3-dimension thermal stress indt^eed by thermal stratification is decoupled to l-dimension global stress and 2-dimension local stress, and the complex 3-dimention problem is simplified into a combination of l-dimension and 2-dimension to compute the stress. Comply with criterion RCC-M, the complete structure integrity evaluation is accomplished after combining the stress produced by thermal stratification and the stresses produced by the other loadings. In order to match the above combined analysis method, Code SYSTUS and ROCOCO are developed. By means of aforesaid evaluation method and corresponding analysis program, surge line thermal stratification of Qinshn Phase II Extension project is investigated in this paper. And the results show that structural integrity of the pressurizer surge line affected by thermal stratification still satisfies criterion RCC-M.
出处 《核动力工程》 EI CAS CSCD 北大核心 2014年第5期31-35,共5页 Nuclear Power Engineering
关键词 稳压器波动管 热分层 换热系数 疲劳 程序开发 Pressurizer surge line, Thermal stratification, Heat transfer coefficient, Fatigue, Proceduredevelopment
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参考文献7

  • 1NRC. Unexpected piping movement attribute to thermal stratification[R].Information Notice 88-80, US: NRC, 1988.
  • 2NRC. Pressurizer surge line thermal stratification[R]. Bulletin 88-11, US: NRC, 1988.
  • 3Structural Integrity Associates(SI). Thermal stratification in piping systems[R]. SIB-96-159, 1996. 12.
  • 4Yu Y J, Park S H, Solm G I-L Structural evaluation of thermal stratification for PWR surge line[J]. Nuclear Engineering and Design, 1997, 178: 211-220.
  • 5Klaus W. Bieniussa, Hands Reck. Piping Specific analysis of stresses due to thermal stratification[J]. Nuclear Engineering and Desig, 1999, 190: 239-249.
  • 6Emel C, Colas A, Barthez M. Stress Analysis of a900MW pressurizer surge line including stratification effects[J]. Nuclear Engineering and Design, 1995, 153: 197-203.
  • 7张毅雄,杨宇.稳压器波动管热分层分析[J].核动力工程,2006,27(6):13-17. 被引量:14

二级参考文献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.
  • 4Ensel 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.
  • 5Jang-Sun Ahn,Eun-Ki Kim,Seoug-Beom Kim Numerical Analysis for Unsteady Thermal Stratifural Turbulent Flow in a Horizontal Circular Cylinder[C].International Conference on Nuclear Engineering 1996,1:1~8.
  • 6Kuo A,A Theoretical Study on Global-Local Stress Decompostion Technique for a Thermally Stratified piping System[J].ASME PVP,1991,210:2.

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