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Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants
Tan, Jibo; Zhang, Ziyu; Zheng, Hui; Wang, Xiang; Gao, Jun; Wu, Xinqiang; Han, En-Hou; Yang, Shuangliang; Huang, Pengtao
2020-12-01
Source PublicationJOURNAL OF NUCLEAR MATERIALS
Volume541
AbstractLow 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.
DOI10.1016/j.jnucmat.2020.152407
WOS IDWOS:000575165800008
Citation statistics
Document Type期刊论文
Identifierhttp://ir.imr.ac.cn/handle/321006/82328
Collection中国科学院金属研究所
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.
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.
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).
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