Corrosion fatigue crack growth behavior of 316LN stainless steel in high-temperature pressurized water
文献类型：期刊论文
| 作者 | Zhang, Ziyu; Tan, Jibo; Wu, Xinqiang; Han, En-Hou; Ke, Wei |
| 刊名 | NUCLEAR ENGINEERING AND TECHNOLOGY
 |
| 出版日期 | 2021-09-01 |
| 卷号 | 53期号:9页码:2977-2981 |
| 关键词 | Stainless steel Fatigue crack growth rate High-temperature water Environmental assisted damage |
| ISSN号 | 1738-5733 |
| DOI | 10.1016/j.net.2021.03.016 |
| 通讯作者 | Wu, Xinqiang(xqwu@imr.ac.cn) |
| 英文摘要 | 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. |
| 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 |
| 语种 | 英语 |
| WOS记录号 | WOS:000677490600007 |
| 出版者 | KOREAN NUCLEAR SOC |
| 资助机构 | 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 |
| 源URL | [http://ir.imr.ac.cn/handle/321006/159708]  |
| 专题 | 金属研究所_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. |
入库方式： OAI收割
来源：金属研究所
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