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CORROSION FATIGUE OF NUCLEAR-GRADE STAINLESS STEEL IN HIGH TEMPERATURE WATER AND ITS ENVIRONMENTAL FATIGUE DESIGN MODEL
Wu Xinqiang1,2; Xu Song1,2; Han En-Hou1,2; Ke Wei1,2
Corresponding AuthorWu Xinqiang(xgwu@imr.ac.cn)
2011-07-11
Source PublicationACTA METALLURGICA SINICA
ISSN0412-1961
Volume47Issue:7Pages:790-796
AbstractThe 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.
Keywordnuclear-grade stainless steel high temperature pressurized water corrosion fatigue environmentally assisted cracking design model
Funding OrganizationNational Basic Research Program of China ; National Science and Technology Major Project
DOI10.3724/SP.J.1037.2011.00162
Indexed BySCI
Language英语
Funding ProjectNational Basic Research Program of China[2011CB610506] ; National Science and Technology Major Project[2011ZX06004-009]
WOS Research AreaMetallurgy & Metallurgical Engineering
WOS SubjectMetallurgy & Metallurgical Engineering
WOS IDWOS:000294980700005
PublisherSCIENCE PRESS
Citation statistics
Cited Times:4[WOS]   [WOS Record]     [Related Records in WOS]
Document Type期刊论文
Identifierhttp://ir.imr.ac.cn/handle/321006/104757
Collection中国科学院金属研究所
Corresponding AuthorWu Xinqiang
Affiliation1.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
Recommended Citation
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.
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