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Crack stability evaluation of nuclear main steam pipe considering load reduction effect

机译:考虑减载效应的核电主蒸汽管裂纹稳定性评估

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The objective of this paper is to evaluate the crack stability of a nuclear main steam pipe. considering load reduction effect due to the presence of circumferential through-wall crack. Also, optimization techniques are adopted to simulate the crack effect on the elbow component of piping systems. By using a general beam element that contains a discontinuous cross-section, piping analysis is performed to obtain the reduced load. Considering this reduced load, LBB design concept is applicable to the nuclear main steam pipe system. Also, by combining an optimization program and a general finite element analysis software, the appropriate dimensions are simplified and an equivalent beam element representing the effect of crack in the elbow could be successfully obtained.
机译:本文的目的是评估核主蒸汽管的裂纹稳定性。考虑到由于周向贯穿壁裂纹的存在而导致的载荷降低效果。另外,采用优化技术来模拟裂纹对管道系统弯头部件的影响。通过使用包含不连续横截面的普通梁单元,进行管道分析以获得减小的载荷。考虑到这种减少的负荷,LBB的设计理念适用于核电主蒸汽管道系统。此外,通过组合优化程序和通用有限元分析软件,可以简化适当的尺寸,并且可以成功获得表示肘部裂纹影响的等效梁单元。

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