Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Multiscale simulations for estimating mechanical properties of ion irradiated 308 based on microstructural features

  • Dong-Hyeon Kwak (Department of Nuclear Engineering, Kyung Hee University) ;
  • Jae Min Sim (Department of Nuclear Engineering, Kyung Hee University) ;
  • Yoon-Suk Chang (Department of Nuclear Engineering, Kyung Hee University) ;
  • Byeong Seo Kong (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Changheui Jang (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology)
  • Received : 2022.12.10
  • Accepted : 2023.05.07
  • Published : 2023.08.25
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Abstract

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.

Keywords

Acknowledgement

This work was supported by the Korea Institute of Energy Technology Evaluation and Planning (KETEP) and the Ministry of Trade, Industry & Energy (MOTIE) of the Republic of Korea (No. 20191510301140).

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