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Monitoring of inside surface crack growth by strain measurement of the outside surface: A feasibility study

机译:通过外表面应变测量监测内表面裂纹扩展:可行性研究

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摘要

Cracks detected by in-service inspections are not always removed when they are judged to be not hazardous according to fitness-for-service evaluations. In order to secure the integrity of the cracked components, it is important to confirm that the cracks do not grow notably beyond the growth prediction conducted for the judgement. However, due to the limitation of accuracy of size determination by the current inspection techniques such as ultrasonic testing, it is difficult to know how much the cracks have grown since their previous measurement. In this study, feasibility of a crack growth monitoring method (outside strain monitoring method) was evaluated by finite element analyses and experiments. When a pipe deforms elastically due to internal pressure, the strain at its outside surface increases. The magnitude of strain near the crack differs from that at an uncracked portion, and the difference depends on the crack size. Elastic finite element analyses were performed for cracked pipes under internal pressure for various crack sizes. It was shown that, by measuring the change in strain at the outside surface of the cracked pipe, the crack size and how much the crack grew can be identified. In the experiment, cracked pipes were subjected to static internal pressure and strains for eight cracks of different sizes were measured. It was revealed that the maximum error was 0.44 mm for the estimation of crack depth of 4 mm and 0.28 mm for the estimation of 1 mm crack growth in the depth direction.
机译:根据适用性评估,如果在使用中检查发现的裂纹没有危险,则并不总是将其消除。为了确保破裂部件的完整性,重要的是要确认裂缝的增长不会明显超过为判断所进行的增长预测。然而,由于当前的检查技术(例如超声测试)对尺寸确定精度的限制,很难知道自从其先前的测量以来裂纹已经发展了多少。在这项研究中,通过有限元分析和实验评估了裂纹扩展监测方法(外部应变监测方法)的可行性。当管道由于内部压力而弹性变形时,其外表面的应变会增加。裂纹附近的应变的大小与未裂纹部分的应变的大小不同,并且该差值取决于裂纹的大小。在内部压力下对各种裂缝尺寸的裂缝管进行了弹性有限元分析。结果表明,通过测量裂纹管外表面的应变变化,可以确定裂纹的大小和裂纹的扩展量。在实验中,对破裂的管道施加静态内压,并测量了八个不同尺寸裂缝的应变。结果表明,裂纹深度为4mm时的最大误差为0.44mm,裂纹扩展量为1mm时的最大误差为0.28mm。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2011年第1期|p.1-11|共11页
  • 作者

    Masayuki Kamaya; Koji Miyoshi;

  • 作者单位

    Institute of Nuclear Safety System, Inc., 64 Sata Mihama-cho, Fukui 919-1205, Japan;

    Institute of Nuclear Safety System, Inc., 64 Sata Mihama-cho, Fukui 919-1205, Japan;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

  • 入库时间 2022-08-18 00:44:29

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