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辐照后铍构件的应力分析与评价 被引量:2

Analysis and Assessment of Reactor Beryllium Component Stress
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摘要 针对铍材的机械性能和辐照特性,在考虑机械应力、热应力、辐照肿胀应力以及按工况进行载荷组合的基础上,对辐照后铍构件的应力进行分析计算,并采用最大拉应力理论进行评价。以高通量工程试验堆(HFETR)铍组件为例,采用ABAQUS软件计算其关键部件铍套管的应力状态。结果显示,其最大主应力远小于材料拉伸强度,从应力破坏的角度看,该铍组件仍可继续使用较长时间。 Based on the mechanical and irradiation properties of beryllium, the irradiated beryllium component stress analysis was proposed, in which the mechanical stress, thermal stress and irradiation swelling induced stress and the load combination in the operation conditions are considered,, and also the maximum tensile stress theory was suggested to use in the assessment. In this paper, a stress analysis and assessment was made for the beryllium tube, which is the key component of HFETR beryllium assembly, by ABAOUS. The result showed that the maximum principle stress was much less than the tensile stress, and that the beryllium assembly can be still used for a long time from the perspective of stress rupture.
出处 《核动力工程》 EI CAS CSCD 北大核心 2014年第6期73-76,共4页 Nuclear Power Engineering
关键词 辐照损伤性能 应力分析和评价 Beryllium, Irradiation damage behaviour, Stress analysis and assessment
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参考文献5

  • 1Beeston J M,Longhurst G R,Wallace R S.Mechanical properties of irradiated beryllium[J].Journal of Nuclear Materials,1992,195:102-108.
  • 2Beeston J M.Properties of irradiated beryllium statistical evaluation[R].Idaho National Engineering and Environmental Laboratory Report,TREE-1063,1976.
  • 3Tomberlin T A.Beryllium–A unique material in nuclear applications[C].36th International SAMPE Technical Conference,2004.
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  • 5冯明全,王云惠,顾剑涛,尹顺玖.HFETR 铍组件辐照后检验及性能评价[J].中国核科技报告,2003(2):121-127. 被引量:5

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