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Corrosion fatigue behavior of Alloy 690 steam generator tube in borated and lithiated high temperature water

机译:690合金蒸汽发生器管在硼酸化和锂化高温水中的腐蚀疲劳行为。

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摘要

Corrosion fatigue behavior of Alloy 690 tube used for actual steam generator (SG) was investigated in <5 ppb (by weight) dissolved oxygen borated and lithiated high temperature water by low cycle fatigue tests with boat-shaped specimens. It was found that the present tube materials had longer fatigue life than round-bar materials in open literature. The surface cracks were tortuous, typical crack branching and linkage were observed. The fracture surfaces were rough with well-defined fatigue striations. Related mechanisms of fatigue crack initiation and propagation of Alloy 690 SG tube in high temperature water are discussed.
机译:通过船形试样的低循环疲劳试验,研究了在小于5 ppb(按重量计)的溶解有氧的硼酸化和锂化高温水中,用于实际蒸汽发生器(SG)的690合金管的腐蚀疲劳行为。在公开文献中发现,本发明的管材料比圆棒材料具有更长的疲劳寿命。表面裂纹是曲折的,观察到典型的裂纹分支和连接。断裂表面是粗糙的,具有明确的疲劳条纹。讨论了690 SG合金在高温水中疲劳裂纹萌生和扩展的相关机理。

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  • 来源
    《Corrosion science》 |2014年第12期|203-213|共11页
  • 作者单位

    University of Science and Technology of China, Hefei 230000, China,Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China;

    Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China;

    Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China;

    Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China;

    Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China;

    Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China;

    Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China;

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

    A. Alloy; B. SEM; C. Corrosion fatigue; C. High temperature corrosion;

    机译:A.合金扫描电镜C.腐蚀疲劳;C.高温腐蚀;

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