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Corrosion fatigue crack growth behaviour of austenitic stainless steels under light water reactor conditions

机译:轻水堆条件下奥氏体不锈钢的腐蚀疲劳裂纹扩展行为

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摘要

The corrosion fatigue crack growth behaviour of different wrought low-carbon and stabilised austenitic stainless steels was characterised under simulated boiling water and primary pressurised water reactor conditions by cyclic fatigue tests with pre-cracked fracture mechanics specimens in the temperature range from 70 to 320℃. The major parameter effects and critical conjoint threshold conditions, which result in relevant environmental acceleration of fatigue crack growth are discussed and summarised. Furthermore, the observed corrosion fatigue behaviour is compared with the corresponding (corrosion) fatigue curves in the ASME and jSME boiler and pressure vessel code or open literature and conclusions with regard to their adequacy and conservatism are given.
机译:通过模拟裂纹水和70℃至320℃温度范围内的预破裂断裂力学试样的循环疲劳试验,在模拟沸水和一次压水反应堆条件下,表征了不同锻造低碳和稳定奥氏体不锈钢的腐蚀疲劳裂纹扩展行为。讨论并总结了导致疲劳裂纹扩展相关环境加速的主要参数效应和临界联合阈值条件。此外,将观察到的腐蚀疲劳行为与ASME和jSME锅炉中的相应(腐蚀)疲劳曲线进行比较,并比较压力容器规范或公开文献,并就其充分性和保守性给出结论。

著录项

  • 来源
    《Corrosion science》 |2012年第2期|p.61-75|共15页
  • 作者单位

    Paul Scherrer Institute (PSI), Nuclear Energy and Safety Research Department. Laboratory for Nuclear Materials, 5232 Villigen PSI. Switzerland;

    Paul Scherrer Institute (PSI), Nuclear Energy and Safety Research Department. Laboratory for Nuclear Materials, 5232 Villigen PSI. Switzerland;

    Paul Scherrer Institute (PSI), Nuclear Energy and Safety Research Department. Laboratory for Nuclear Materials, 5232 Villigen PSI. Switzerland;

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  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    A. Stainless steel; C. Corrosion fatigue; C. Reactor conditions;

    机译:A.不锈钢;C.腐蚀疲劳;C.反应堆条件;

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