| Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants | |
| Tan, Jibo1; Zhang, Ziyu1; Zheng, Hui2; Wang, Xiang1; Gao, Jun1; Wu, Xinqiang1; Han, En-Hou1; Yang, Shuangliang2; Huang, Pengtao2 | |
| Corresponding Author | Wu, Xinqiang(xqwu@imr.ac.cn) |
| 2020-12-01 | |
| Source Publication | JOURNAL OF NUCLEAR MATERIALS
 |
| ISSN | 0022-3115 |
| Volume | 541Pages:10 |
| Abstract | 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. |
| Keyword | Corrosion fatigue Austenitic stainless steel High temperature corrosion Model |
| Funding Organization | 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 |
| DOI | 10.1016/j.jnucmat.2020.152407 |
| Indexed By | SCI |
| Language | 英语 |
| Funding Project | 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 Research Area | Materials Science ; Nuclear Science & Technology |
| WOS Subject | Materials Science, Multidisciplinary ; Nuclear Science & Technology |
| WOS ID | WOS:000575165800008 |
| Publisher | ELSEVIER |
| Citation statistics | |
| Document Type | 期刊论文 |
| Identifier | http://ir.imr.ac.cn/handle/321006/140824 |
| Collection | 中国科学院金属研究所 |
| Corresponding Author | Wu, Xinqiang |
| Affiliation | 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.State Nucl Power Plant Serv Co, Shanghai 200233, Peoples R China |
| Recommended Citation 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. |
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