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

doi:10.3724/SP.J.1037.2011.00162

IMR OpenIR

	CORROSION FATIGUE OF NUCLEAR-GRADE STAINLESS STEEL IN HIGH TEMPERATURE WATER AND ITS ENVIRONMENTAL FATIGUE DESIGN MODEL
	Wu Xinqiang 1,2; Xu Song 1,2; Han En-Hou 1,2; Ke Wei 1,2
通讯作者	Wu Xinqiang(xgwu@imr.ac.cn)
	2011-07-11
发表期刊	ACTA METALLURGICA SINICA
ISSN	0412-1961
卷号	47 期号:7 页码:790-796
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.
关键词	nuclear-grade stainless steel high temperature pressurized water corrosion fatigue environmentally assisted cracking design model
资助者	National Basic Research Program of China ; National Science and Technology Major Project
DOI	10.3724/SP.J.1037.2011.00162
收录类别	SCI
语种	英语
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
WOS类目	Metallurgy & Metallurgical Engineering
WOS记录号	WOS:000294980700005
出版者	SCIENCE PRESS
引用统计	被引频次：5[WOS] [WOS记录] [WOS相关记录]
文献类型	期刊论文
条目标识符	http://ir.imr.ac.cn/handle/321006/104757
专题	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.