Environmental fatigue correction factor model for domestic nuclear-grade low-alloy steel

doi:10.1016/j.net.2021.02.014

IMR OpenIR

	Environmental fatigue correction factor model for domestic nuclear-grade low-alloy steel
	Gao, Jun 1,2; Liu, Chang 3; Tan, Jibo 1; Zhang, Ziyu 1; Wu, Xinqiang 1; Han, En-Hou 1; Shen, Rui 3; Wang, Bingxi 3; Ke, Wei 1
通讯作者	Tan, Jibo(jbtan10s@imr.ac.cn)
	2021-08-01
发表期刊	NUCLEAR ENGINEERING AND TECHNOLOGY
ISSN	1738-5733
卷号	53 期号:8 页码:2600-2609
摘要	Low cycle fatigue behaviors of SA508-3 low-alloy steel were investigated in room-temperature air, high temperature air and in light water reactor (LWR) water environments. The fatigue mean curve and design curve for the low-alloy steel are developed based on the fatigue data in room-temperature and high temperature air. The environmental fatigue model for low-alloy steel is developed by the environmental fatigue correction factor (F-en) methodology based on the fatigue data in LWR water environments with the consideration of effects of strain rate, temperature, and dissolved oxygen concentration on the fatigue life. (C) 2021 Korean Nuclear Society, Published by Elsevier Korea LLC.
关键词	Low cycle fatigue Low-alloy steel Environmental assisted fatigue Design codes
资助者	National Science and Technology Major Project ; Key Programs of the Chinese Academy of Sciences (Research on the Development of Nuclear Power Materials and Service Security Technology) ; National Natural Science Foundation of China ; Innovation Fund of Institute of Metal Research, Chinese Academy of Sciences
DOI	10.1016/j.net.2021.02.014
收录类别	SCI
语种	英语
资助项目	National Science and Technology Major Project[2017ZX06002003-004-002] ; Key Programs of the Chinese Academy of Sciences (Research on the Development of Nuclear Power Materials and Service Security Technology)[ZDRW-CN-2017-1] ; National Natural Science Foundation of China[51601201] ; National Natural Science Foundation of China[51671201] ; Innovation Fund of Institute of Metal Research, Chinese Academy of Sciences[SCJJ-2013-ZD-02]
WOS研究方向	Nuclear Science & Technology
WOS类目	Nuclear Science & Technology
WOS记录号	WOS:000671556100002
出版者	KOREAN NUCLEAR SOC
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/321006/159985
专题	中国科学院金属研究所
通讯作者	Tan, Jibo
作者单位	1.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 2.Univ Sci & Technol China, Sch Mat Sci & Engn, Hefei 230026, Peoples R China 3.Shanghai Nucl Engn Res & Design Inst, Shanghai 200233, Peoples R China
推荐引用方式 GB/T 7714	Gao, Jun,Liu, Chang,Tan, Jibo,et al. Environmental fatigue correction factor model for domestic nuclear-grade low-alloy steel[J]. NUCLEAR ENGINEERING AND TECHNOLOGY,2021,53(8):2600-2609.
APA	Gao, Jun.,Liu, Chang.,Tan, Jibo.,Zhang, Ziyu.,Wu, Xinqiang.,...&Ke, Wei.(2021).Environmental fatigue correction factor model for domestic nuclear-grade low-alloy steel.NUCLEAR ENGINEERING AND TECHNOLOGY,53(8),2600-2609.
MLA	Gao, Jun,et al."Environmental fatigue correction factor model for domestic nuclear-grade low-alloy steel".NUCLEAR ENGINEERING AND TECHNOLOGY 53.8(2021):2600-2609.