CORROSION FATIGUE OF NUCLEAR-GRADE STAINLESS STEEL IN HIGH TEMPERATURE WATER AND ITS ENVIRONMENTAL FATIGUE DESIGN MODEL
文献类型：期刊论文
| 作者 | Wu Xinqiang1,2; Xu Song1,2; Han En-Hou1,2; Ke Wei1,2 |
| 刊名 | ACTA METALLURGICA SINICA
 |
| 出版日期 | 2011-07-11 |
| 卷号 | 47期号:7页码:790-796 |
| 关键词 | nuclear-grade stainless steel high temperature pressurized water corrosion fatigue environmentally assisted cracking design model |
| ISSN号 | 0412-1961 |
| DOI | 10.3724/SP.J.1037.2011.00162 |
| 通讯作者 | Wu Xinqiang(xgwu@imr.ac.cn) |
| 英文摘要 | 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. |
| 资助项目 | National Basic Research Program of China[2011CB610506] ; National Science and Technology Major Project[2011ZX06004-009] |
| WOS研究方向 | Metallurgy & Metallurgical Engineering |
| 语种 | 英语 |
| WOS记录号 | WOS:000294980700005 |
| 出版者 | SCIENCE PRESS |
| 资助机构 | National Basic Research Program of China ; National Science and Technology Major Project |
| 源URL | [http://ir.imr.ac.cn/handle/321006/104756]  |
| 专题 | 金属研究所_中国科学院金属研究所 |
| 通讯作者 | Wu Xinqiang |
| 作者单位 | 1.Chinese Acad Sci, Inst Met Res, State Key Lab Corros & Protect, Shenyang 110016, Peoples R China 2.Chinese Acad Sci, Inst Met Res, Liaoning Key Lab Safety & Assessment Tech Nucl Ma, Shenyang 110016, Peoples R China |
| 推荐引用方式 GB/T 7714 | Wu Xinqiang,Xu Song,Han En-Hou,et al. CORROSION FATIGUE OF NUCLEAR-GRADE STAINLESS STEEL IN HIGH TEMPERATURE WATER AND ITS ENVIRONMENTAL FATIGUE DESIGN MODEL[J]. ACTA METALLURGICA SINICA,2011,47(7):790-796. |
| APA | Wu Xinqiang,Xu Song,Han En-Hou,&Ke Wei.(2011).CORROSION FATIGUE OF NUCLEAR-GRADE STAINLESS STEEL IN HIGH TEMPERATURE WATER AND ITS ENVIRONMENTAL FATIGUE DESIGN MODEL.ACTA METALLURGICA SINICA,47(7),790-796. |
| MLA | Wu Xinqiang,et al."CORROSION FATIGUE OF NUCLEAR-GRADE STAINLESS STEEL IN HIGH TEMPERATURE WATER AND ITS ENVIRONMENTAL FATIGUE DESIGN MODEL".ACTA METALLURGICA SINICA 47.7(2011):790-796. |
入库方式： OAI收割
来源：金属研究所
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