IMR OpenIR
Corrosion fatigue behavior and crack-tip characteristic of 316LN stainless steel in high-temperature pressurized water
Zhang, Ziyu1,2; Tan, Jibo1; Wu, Xinqiang1; Han, En-Hou1; Ke, Wei1; Rao, Jiancun1,3
通讯作者Wu, Xinqiang(xqwu@imr.ac.cn)
2019-05-01
发表期刊JOURNAL OF NUCLEAR MATERIALS
ISSN0022-3115
卷号518页码:21-29
摘要The corrosion fatigue (CF) behavior and crack tip characteristic of 316LN stainless steel in 325 degrees C water at different strain rates were investigated under a strain amplitude of 0.6%. With decreasing the strain rate from 0.4% s(-1) to 0.0004% s(-1), the CF life decreased linearly in log-log plot. More obvious reduction of CF life at low strain rate was due to the environmental damage. The morphology of cracks and the dislocation density near the crack-tip front exhibit a significant different under different strain rate conditions. The hydrogen enhanced localized plasticity mechanism is discussed to explain the micro-damage process at different strain rates in high-temperature water. (C) 2019 Elsevier B.V. All rights reserved.
关键词Stainless steel Corrosion fatigue Crack-tip structure High-temperature water Environmental damage
资助者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 ; National Research Council of Science and Technology Major Project ; Innovation Fund of Institute of Metal Research, Chinese Academy of Sciences
DOI10.1016/j.jnucmat.2019.02.040
收录类别SCI
语种英语
资助项目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] ; National Research Council of Science and Technology Major Project[2017ZX06002003-004-002] ; Innovation Fund of Institute of Metal Research, Chinese Academy of Sciences[SCJJ-2013-ZD-02]
WOS研究方向Materials Science ; Nuclear Science & Technology
WOS类目Materials Science, Multidisciplinary ; Nuclear Science & Technology
WOS记录号WOS:000464940700003
出版者ELSEVIER SCIENCE BV
引用统计
被引频次:23[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/321006/132753
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, CAS Key Lab Nucl Mat & Safety Assessment, Liaoning Key Lab Safety & Assessment Tech Nucl Ma, Shenyang 110016, Liaoning, Peoples R China
2.Univ Chinese Acad Sci, Ctr Mat Sci & Optoelect Engn, Beijing 100049, Peoples R China
3.Harbin Inst Technol, Harbin 150001, Heilongjiang, Peoples R China
推荐引用方式
GB/T 7714
Zhang, Ziyu,Tan, Jibo,Wu, Xinqiang,et al. Corrosion fatigue behavior and crack-tip characteristic of 316LN stainless steel in high-temperature pressurized water[J]. JOURNAL OF NUCLEAR MATERIALS,2019,518:21-29.
APA Zhang, Ziyu,Tan, Jibo,Wu, Xinqiang,Han, En-Hou,Ke, Wei,&Rao, Jiancun.(2019).Corrosion fatigue behavior and crack-tip characteristic of 316LN stainless steel in high-temperature pressurized water.JOURNAL OF NUCLEAR MATERIALS,518,21-29.
MLA Zhang, Ziyu,et al."Corrosion fatigue behavior and crack-tip characteristic of 316LN stainless steel in high-temperature pressurized water".JOURNAL OF NUCLEAR MATERIALS 518(2019):21-29.
条目包含的文件
条目无相关文件。
个性服务
推荐该条目
保存到收藏夹
查看访问统计
导出为Endnote文件
谷歌学术
谷歌学术中相似的文章
[Zhang, Ziyu]的文章
[Tan, Jibo]的文章
[Wu, Xinqiang]的文章
百度学术
百度学术中相似的文章
[Zhang, Ziyu]的文章
[Tan, Jibo]的文章
[Wu, Xinqiang]的文章
必应学术
必应学术中相似的文章
[Zhang, Ziyu]的文章
[Tan, Jibo]的文章
[Wu, Xinqiang]的文章
相关权益政策
暂无数据
收藏/分享
所有评论 (0)
暂无评论
 

除非特别说明,本系统中所有内容都受版权保护,并保留所有权利。