Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants
文献类型：期刊论文
| 作者 | Tan, Jibo2; Zhang, Ziyu2; Zheng, Hui1; Wang, Xiang2; Gao, Jun2; Wu, Xinqiang2; Han, En-Hou2; Yang, Shuangliang1; Huang, Pengtao1 |
| 刊名 | JOURNAL OF NUCLEAR MATERIALS
 |
| 出版日期 | 2020-12-01 |
| 卷号 | 541页码:10 |
| ISSN号 | 0022-3115 |
| 关键词 | Corrosion fatigue Austenitic stainless steel High temperature corrosion Model |
| DOI | 10.1016/j.jnucmat.2020.152407 |
| 通讯作者 | Wu, Xinqiang(xqwu@imr.ac.cn) |
| 英文摘要 | Low cycle fatigue behavior of 316LN stainless steel (SS), 304 SS and 308L weld metal was investigated in air and high-temperature pressurized water environment. The effects of mechanical factors and environmental factors on fatigue lives were considered. The fatigue mean curve and design curve for nucleargrade austenitic SSs in air are obtained by fitting fatigue data. The corrosion fatigue model for nucleargrade austenitic SSs in high-temperature pressurized water environment is proposed based on environmental fatigue correction factor method, which mainly considers the effects of strain rate, temperature and dissolved oxygen concentration. (C) 2020 Elsevier B.V. All rights reserved. |
| 资助项目 | National Key R&D Program of China[2017YFB0702103] ; National Science and Technology Major Project[2015ZX06002005] ; National Science and Technology Major Project[2017ZX06002003-004-002] ; National Natural Science Foundation of China[51671201] ; Chinese Academy of Sciences[ZDRW-CN-2017-1] ; Institute of Metal Research, Chinese Academy of Sciences[SCJJ-2013-ZD-02] |
| WOS研究方向 | Materials Science ; Nuclear Science & Technology |
| 语种 | 英语 |
| 出版者 | ELSEVIER |
| WOS记录号 | WOS:000575165800008 |
| 资助机构 | National Key R&D Program of China ; National Science and Technology Major Project ; National Natural Science Foundation of China ; Chinese Academy of Sciences ; Institute of Metal Research, Chinese Academy of Sciences |
| 源URL | [http://ir.imr.ac.cn/handle/321006/140826]  |
| 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 | 1.State Nucl Power Plant Serv Co, Shanghai 200233, Peoples R China 2.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 | Tan, Jibo,Zhang, Ziyu,Zheng, Hui,et al. Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants[J]. JOURNAL OF NUCLEAR MATERIALS,2020,541:10. |
| APA | Tan, Jibo.,Zhang, Ziyu.,Zheng, Hui.,Wang, Xiang.,Gao, Jun.,...&Huang, Pengtao.(2020).Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants.JOURNAL OF NUCLEAR MATERIALS,541,10. |
| MLA | Tan, Jibo,et al."Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants".JOURNAL OF NUCLEAR MATERIALS 541(2020):10. |
入库方式： OAI收割
来源：金属研究所
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