材料科学
辐照
微观结构
奥氏体
结构材料
铁氧体(磁铁)
中子
复合材料
穿透深度
中子通量
位错
核物理学
光学
物理
作者
Dong-Hyeon Kwak,Jae Min Sim,Yoon‐Suk Chang,Byeong Seo Kong,Changheui Jang
标识
DOI:10.1016/j.net.2023.05.011
摘要
Austenitic stainless steel welds (ASSWs) of nuclear components undergo aging-related degradations caused by high temperature and neutron radiation. Since irradiation leads to the change of material characteristics, relevant quantification is important for long-term operation, but limitations exist. Although ion irradiation is utilized to emulate neutron irradiation, its penetration depth is too shallow to measure bulk properties. In this study, a systematic approach was suggested to estimate mechanical properties of ion irradiated 308 ASSW. First of all, weld specimens were irradiated by 2 MeV proton to 1 and 10 dpa. Microstructure evolutions due to irradiation in δ-ferrite and austenite phases were characterized and micropillar compression tests were performed. In succession, dislocation density based stress-strain (S–S) relationships and quantification models of irradiation defects were adopted to define phases in finite element analyses. Resultant microscopic S–S curves were compared to verify material parameters. Finally, macroscopic behaviors were calculated by multiscale simulations using real microstructure based representative volume element (RVE). Validity of the approach was verified for the unirradiated specimens such that the estimated S–S curves and 0.2% offset yield strengths (YSs) which was 363.14 MPa were in 10% agreement with test. For irradiated specimens, the estimated YS were 917.41 MPa in 9% agreement.
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