Corrosion fatigue crack growth behavior of 316LN stainless steel in high-temperature pressurized water

doi:10.1016/j.net.2021.03.016

IMR OpenIR

	Corrosion fatigue crack growth behavior of 316LN stainless steel in high-temperature pressurized water
	Zhang, Ziyu; Tan, Jibo; Wu, Xinqiang; Han, En-Hou; Ke, Wei
通讯作者	Wu, Xinqiang(xqwu@imr.ac.cn)
	2021-09-01
发表期刊	NUCLEAR ENGINEERING AND TECHNOLOGY
ISSN	1738-5733
卷号	53 期号:9 页码:2977-2981
摘要	Corrosion fatigue crack growth (FCG) behavior of 316LN stainless steel was investigated in high-temperature pressurized water at different temperatures, load ratios (R = K-max/K-min) and rise times (t(R)). The environmental assisted effect on FCG rate was observed when both the R and tR exceeded their critical values. The FCG rate showed a linear relation with stress intensity factor range (Delta K) in double logarithmic coordinate. The environmental assisted effect on FCG rate depended on the Delta K and quantitative relations were proposed. Possible mechanisms of environmental assisted FCG rate under different testing conditions are also discussed. (C) 2021 Korean Nuclear Society, Published by Elsevier Korea LLC.
关键词	Stainless steel Fatigue crack growth rate High-temperature water Environmental assisted damage
资助者	Natural Science Foundation of Liaoning Province of China ; Open Foundation of CAS Key Laboratory of Nuclear Materials and Safety Assessment ; National Science and Technology Major Project ; CNNC Science Fund for Talented Young Scholars
DOI	10.1016/j.net.2021.03.016
收录类别	SCI
语种	英语
资助项目	Natural Science Foundation of Liaoning Province of China[2020-BS-005] ; Open Foundation of CAS Key Laboratory of Nuclear Materials and Safety Assessment[292020000038] ; National Science and Technology Major Project[2017ZX06002003-004-002] ; CNNC Science Fund for Talented Young Scholars
WOS研究方向	Nuclear Science & Technology
WOS类目	Nuclear Science & Technology
WOS记录号	WOS:000677490600007
出版者	KOREAN NUCLEAR SOC
引用统计	被引频次：4[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/321006/159709
专题	中国科学院金属研究所
通讯作者	Wu, Xinqiang
作者单位	Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Liaoning Key Lab Safety & Assessment Tech Nucl Ma, Shenyang 110016, Peoples R China
推荐引用方式 GB/T 7714	Zhang, Ziyu,Tan, Jibo,Wu, Xinqiang,et al. Corrosion fatigue crack growth behavior of 316LN stainless steel in high-temperature pressurized water[J]. NUCLEAR ENGINEERING AND TECHNOLOGY,2021,53(9):2977-2981.
APA	Zhang, Ziyu,Tan, Jibo,Wu, Xinqiang,Han, En-Hou,&Ke, Wei.(2021).Corrosion fatigue crack growth behavior of 316LN stainless steel in high-temperature pressurized water.NUCLEAR ENGINEERING AND TECHNOLOGY,53(9),2977-2981.
MLA	Zhang, Ziyu,et al."Corrosion fatigue crack growth behavior of 316LN stainless steel in high-temperature pressurized water".NUCLEAR ENGINEERING AND TECHNOLOGY 53.9(2021):2977-2981.