论文

核级不锈钢高温水腐蚀疲劳机制及环境疲劳设计模型

  • 吴欣强
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  • 1) 中国科学院金属研究所金属腐蚀与防护国家重点实验室, 沈阳 110016
    2) 中国科学院金属研究所辽宁省核电材料安全与评价技术重点实验室, 沈阳 110016
吴欣强, 男, 1971年生, 研究员

收稿日期: 2011-03-23

  修回日期: 2011-04-11

  网络出版日期: 2011-07-11

基金资助

国家重点基础研究发展计划项目2011CB610506和国家科技重大专项项目2011ZX06004--009资助

CORROSION FATIGUE OF NUCLEAR--GRADE STAINLESS STEEL IN
HIGH TEMPERATURE WATER AND ITS ENVIRONMENTAL FATIGUE DESIGN MODEL

  • WU Xin-Jiang
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  • 1) State Key Laboratory for Corrosion and Protection, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016
    2) Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Material, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016

Received date: 2011-03-23

  Revised date: 2011-04-11

  Online published: 2011-07-11

Supported by

Supported by National Basic Research Program of China (No.2011CB610506) and National Science and Technology Major Project (No.2011ZX06004-009)

摘要

通过模拟核电高温高压循环水腐蚀疲劳实验, 研究了国产核级不锈钢的环境疲劳损伤行为与失效机制; 评价了影响不锈钢高温高压水疲劳寿命的环境和载荷等因素, 建立了一个植入环境损伤效应的疲劳设计模型, 给出了便于工程应用的核级不锈钢的环境疲劳设计曲线.

本文引用格式

吴欣强 . 核级不锈钢高温水腐蚀疲劳机制及环境疲劳设计模型[J]. 金属学报, 2011 , 47(7) : 790 -796 . DOI: 10.3724/SP.J.1037.2011.00162

Abstract

The high safety of light water reactor nuclear power plants (NPPs) requires very strict design standard and service property of pressure boundary components materials. The service degradation and life assessment of the components materials primarily depend on the understanding of environmentally assisted failure mechanism, accumulation of service property data and construction of evaluation models. Currently domestic NPPs are relying on foreign design, operation and life assessment standards. However, recent experimental data indicate that even the ASME design fatigue code may be deficient in safety margin under certain conditions of loading and environment. In the present work, based on the corrosion fatigue tests in simulated NPPs' high temperature pressurized water, the corrosion fatigue behavior and environmentally assisted failure mechanism of domestic nuclear-grade stainless steel have been investigated. The factors affecting fatigue life of nuclear grade stainless steel in high temperature water were evaluated. A design fatigue model was constructed by taking environmental degradation effects into account and the corresponding design curves were given for the convenience of engineering applications.

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