压力容器2025，Vol.42Issue(4)：24-33,10.DOI:10.3969/j.issn.1001-4837.2025.04.004
核级316H不锈钢U型缺口试样的蠕变-疲劳损伤交互机理研究
Study on creep-fatigue damage interaction mechanism in nuclear-grade 316H stainless steel U-notched specimens
沈睿 1唐力晨 1胡靖东1
作者信息
- 1. 上海核工程研究设计院股份有限公司,上海 200233
- 折叠
摘要
Abstract
Taking 316H stainless steel,a key structural material for fourth-generation nuclear reactors,as the research object,creep-fatigue tests were conducted on specimens with U-notches of different sharpness at temperatures of 550～650℃,hold times of 120～900 s,strain amplitude of±0.20%,and strain rate of 0.001%/s.Combining fracture morphology and microstructural analysis,the creep-fatigue fracture mechanism under multiaxial stress states was revealed.Results show that U-notches significantly weaken creep-fatigue performance,reducing cyclic life and fracture time by more than 50%.When the notch sharpness parameter d/r is less than 17.14(corresponding to notch root radius r≥0.35 mm),notch size has no significant effect on creep-fatigue life.All U-notched specimens exhibit similar fracture characteristics:cracks initiate from fracture surfaces,and the number of initiation sites increases with notch size.This research provides reference for failure mechanism of creep fatigue for nuclear grade 316H stainless steel under multi-axis stress condition.关键词
316H不锈钢/蠕变-疲劳/U型缺口试样/滞回曲线/应力松弛/断口形貌Key words
316H stainless steel/creep-fatigue/U-notched specimen/hysteresis loop/stress relaxation/fracture morphology分类
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沈睿,唐力晨,胡靖东..核级316H不锈钢U型缺口试样的蠕变-疲劳损伤交互机理研究[J].压力容器,2025,42(4):24-33,10.
