Environmental fatigue correction factor model for domestic nuclear-grade low-alloy steel

Jun Gao; Chang Liu; Jibo Tan; Ziyu Zhang; Xinqiang Wu; En-Hou Han; Rui Shen; Bingxi Wang; Wei Ke

Nuclear Engineering and Technology (Aug 2021)

Environmental fatigue correction factor model for domestic nuclear-grade low-alloy steel

Jun Gao,
Chang Liu,
Jibo Tan,
Ziyu Zhang,
Xinqiang Wu,
En-Hou Han,
Rui Shen,
Bingxi Wang,
Wei Ke

Affiliations

Jun Gao: CAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang, 110016, PR China; School of Materials Science and Engineering, University of Science and Technology of China, Hefei, 230026, PR China
Chang Liu: Shanghai Nuclear Engineering Research and Design Institute, Shanghai, 200233, PR China
Jibo Tan: CAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang, 110016, PR China; Corresponding author.
Ziyu Zhang: CAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang, 110016, PR China
Xinqiang Wu: CAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang, 110016, PR China
En-Hou Han: CAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang, 110016, PR China
Rui Shen: Shanghai Nuclear Engineering Research and Design Institute, Shanghai, 200233, PR China
Bingxi Wang: Shanghai Nuclear Engineering Research and Design Institute, Shanghai, 200233, PR China
Wei Ke: CAS Key Laboratory of Nuclear Materials and Safety Assessment, Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang, 110016, PR China

Journal volume & issue: Vol. 53, no. 8
pp. 2600 – 2609

Abstract

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Low cycle fatigue behaviors of SA508-3 low-alloy steel were investigated in room-temperature air, high-temperature air and in light water reactor (LWR) water environments. The fatigue mean curve and design curve for the low-alloy steel are developed based on the fatigue data in room-temperature and high-temperature air. The environmental fatigue model for low-alloy steel is developed by the environmental fatigue correction factor (Fen) methodology based on the fatigue data in LWR water environments with the consideration of effects of strain rate, temperature, and dissolved oxygen concentration on the fatigue life.

Published in Nuclear Engineering and Technology

ISSN: 1738-5733 (Print)
Publisher: Elsevier
Country of publisher: Korea, Republic of
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: http://www.journals.elsevier.com/nuclear-engineering-and-technology

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