Crack Growth Simulation Using Iterative Crack-Tip Modeling Technique

Gi-bum Lee, Y. Jang, N. Huh, Sung Hoon Park, Noh-hwan Park, Jun-Hui Park, Kyoungsoo Park
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Abstract

Because of the long-term operation of nuclear power plants, the assessment of crack growth in pipelines has become one of the most important issues. Crack growth resistance in operating nuclear power plants is typically evaluated using linear elastic fracture mechanics based on ASME B&PV Section XI. However, the ASME method predicts the results conservatively, for complex shapes and conditions, while the finite element analysis, which is more accurate, consumes a substantial amount of time and cost. In this study, a finite element analysis-based iterative crack growth program was created to evaluate cracks with more accuracy and time efficiency. The verification of the program was carried out in two cases. By comparing the produced program with the test result of the three-point bending of the beam with rivet holes, it was shown that the program simulates crack propagation in the right direction. In addition, by comparing the results of the fatigue crack growth (FCG) test of CCT/SENT specimens, it was shown that the program can be applied to the evaluation of major failure mechanisms in the nuclear power plants such as stress corrosion crack (SCC) growth and FCG.
基于迭代裂纹尖端建模技术的裂纹扩展模拟
由于核电站的长期运行,管道裂纹扩展的评估已成为最重要的问题之一。然而,对于复杂的形状和条件,ASME方法预测结果保守,而更准确的有限元分析消耗了大量的时间和成本。在本研究中,创建了基于有限元分析的迭代裂纹扩展程序,以更高的精度和时间效率来评估裂纹。在两个案例中对程序进行了验证。将所编制的程序与带铆钉孔的梁的三点弯曲试验结果进行比较,结果表明所编制的程序能够正确地模拟裂纹的扩展方向。此外,通过对比CCT/SENT试件疲劳裂纹扩展(FCG)试验结果,表明该程序可用于评价应力腐蚀裂纹扩展(SCC)和疲劳裂纹扩展(FCG)等核电站主要失效机制。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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