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两环路核电厂试验支管振动疲劳研究 被引量:2

Vibration Fatigue Study of the Testing Branch Pipes in Two-Loop Nuclear Power Plants
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摘要 针对国内二代改进型的两环路核电厂试验用支管中存在的振动疲劳问题,文章提出了一种确定疲劳振动的测量和计算分析方法,并运用该方法对国内某两环路核电厂小支管进行了工况分析、振动测量和最大有效振动速度计算,同时采用结构力学有限元程序ANSYS软件对小支管的振动疲劳应力进行了分析。结果表明,该方法能够很好地诊断出小支管中存在的第一类敏感管和第二类敏感管,从而为判断在两环路核电厂试验中支管是否为敏感管提供了理论依据。 As for the vibration fatigue problems existed in branch pipesused for test of domestic generation Ⅱ+ two-loop nuclear power plant, a measurement and calculation analysis method for identifying fatigue vibration is proposed, which is applied to carry out condition analysis, vibration measurement and maximum effective vibration speed calculation for small branch pipes of a domestic two-loop nuclear power plant. At the same time, the structural mechanics fi-nite element application program ANSYS is used to analyze the vibration fatigue stress of small branch pipes. The result shows that this method can diagnose the first type and the second type of sensitive pipes existed in small branch pipes. Thus, it can provide the theoreticalbasis for de-termining whether there are sensitive pipes in the branch pipes used for test of two-loop nuclear power plant.
出处 《中国核电》 2015年第3期208-213,共6页 China Nuclear Power
关键词 试验支管 振动疲劳 ANSYS test branchpipes ANSYS vibration fatigue
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  • 1STEPHAN J M.Mechanieal Aspects Concerning Thermal Fatigue Initiation in the Mixing Zones of Piping[].th International Conference on Structural Mechanics in Reactor Technology.2005
  • 2LARA P F,WALKER S M.NDE Technology for Detection of Thermal Fatigue Damage in Piping[].EPR Technical Report.2000
  • 3HIRSCHBERG P.Mitigation of Thennal Fatigue in Unisolable Piping Connected to PWR Reactor Coolant Systems[].EPRI Technical Report.2000
  • 4U.S.NRC.Thermal Stresses in Piping Connected to Reactor Coolant Systems. NRC Bulletin NO.88-08 . 1988
  • 5朱维宇,卢涛,姜培学,郭志军,王奎升.T型管中冷热流体混合过程热波动大涡模拟[J].应用数学和力学,2009,30(11):1295-1306. 被引量:11

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