期刊文献+

稳压器波动管热分层应力及疲劳分析 被引量:8

Thermal Stratification and Fatigue Stress Analysis for Pressurizer Surge Line
下载PDF
导出
摘要 稳压器波动管内流体的温度分层引起管壁温度分层,从而在管道截面产生整体弯曲应力、局部热应力以及管道系统超过预期的位移和支撑载荷。将稳压器波动管的热分层这种复杂的三维应力分析问题简化为一维和二维组合问题,利用SYSTUS程序和ROCOCO程序对秦山核电二期扩建工程稳压器波动管热分层的应力及疲劳进行了分析研究,计算了考虑热分层情况下管道的最大应力和疲劳使用系数。分析结果表明,管道在热分层效应下的应力、疲劳强度均满足RCC-M规范相关要求。 Thermal stratification of pressurizer surge line induced by the inside fluid results in the global bending moments,local thermal stresses,unexpected displacements and support loadings of the pipe system.In order to avoid a costly three-dimensional computation,a combined 1D/2D technique has been developed and implemented to analyze the thermal stratification and fatigue stress of pressurize surge line of QINSHAN Phase II Extension Nuclear Power Project in this paper,using the computer codes SYSTUS and ROCOCO.According to the mechanical analysis results of stratification,the maximum stress and cumulative usage factor are obtained.The results indicate that the stress and fatigue intensity considering thermal stratification satisfies RCC-M criterion.
出处 《核动力工程》 EI CAS CSCD 北大核心 2011年第1期6-9,20,共5页 Nuclear Power Engineering
关键词 稳压器波动管 热分层 应力 疲劳 Pressurizer surge line Thermal stratification Stress Fatigue
  • 相关文献

参考文献6

  • 1NRC Bulletin 88-08. Thermal Stresses in Piping Connected to Reactor Coolant Systems [S].
  • 2NRC Bulletin 88-11. Pressurizer Surge Line Thermal Stratification [S].
  • 3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
  • 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.
  • 5Framatome. Stress Analysis Report Pressurizer Surge Line French 900 MWe Plants [R]. EER-01.720,2001.
  • 6AFCEN.RCC-M规范[S].2000版加2002补遗.

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.

共引文献13

同被引文献42

  • 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
  • 3于勇.FLUENT入门与进阶教程[M].北京:北京理工大学出版社,2008.
  • 4TOKUHIRO A, KIMURA N. An experimental investigation on thermal striping: Mixing phe-nomena of a vertical non-buoyant jet with two ad jacent buoyant jets as measured by ultrasound Doppler velocimetry[J].Nuclear Engineering and Design, 1999, 188(1): 49 73.
  • 5CHACKO S, CHUNG Y M, CHOI S K, et al. Large-eddy simulation of thermal striping in un- steady non-isothermal triple jet[J]. International Journal of Heat and Mass Transfer, 2011, 54 (19-20): 4 400-4 409.
  • 6LU D, CAO Q, LV J, et al. Experimental study on three-dimensional temperature fluctuation caused by coaxial-jet flows [J]. Nuclear Engi- neering and Design, 2012, 243(2) : 234-242.
  • 7Kweon H D, Kim J S, Lee K Y. Fatigue design of nuclear class 1 piping considering thermal stratification[J]. Nuclear Engineering and Design, 2008, 238(6): 1265-1274.
  • 8Kim Y J, Kim M W, Ko E, et al. Effect of heat-up transient condition on the thermal stratification in unclear power plant surgeline[C]//Proceedings of the ASME 2009 Pressure Vessels and Piping Division Conference, Prague, Czech Republic, 2009.
  • 9Charles E. Rossi. Thermal stresses in piping connected to reactor coolant systems[EB/OL]. Washington, DC: U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation. http://www.nrc.gov/reading-rm/doc- collections/gen-comm/bulletins/1988/b188008.html.
  • 10Charles E Rossi. Pressurizer surge line thermal stratification[EB/OL]. Washington, DC: U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation. http://www.nrc.gov/reading-rm/doc-collections/ gen-comm/bulletins/1988/b188011.html.

引证文献8

二级引证文献17

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部