About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
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Symposium
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Transmutation Effects in Fusion Reactor Materials: Critical Challenges & Path Forward
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Presentation Title |
Grain-boundary Effects on the Irradiated Damages in W-Re Alloys |
Author(s) |
Sanghyuk Yoo, Younggak Shin, Seunghwan Oh, Hyoungrul Park, Younghyun Kim, Anseung Yoo, Ohkyoung Kwon, Keonwook Kang, Byeongchan Lee |
On-Site Speaker (Planned) |
Byeongchan Lee |
Abstract Scope |
Under irradiated damages lies a mobility discrepancy between vacancies and self-interstitial atoms (SIAs). In W-Re alloys, Re atoms in W, either as solutes or transmutated elements, reduce the mobility of SIAs, buying time for Frenkel pairs to recombine, retarding damages. The presence of grain boundaries changes the irradiated damages working as a sink of interstitials. In particular, ultrafine grains found in a thin-film specimen or a sintered sample have a larger net grain-boundary area, and at the same time, a shorter distance for SIAs to travel to a grain boundary, necessarily changing the defect kinetics. Here, we report the irradiated damages in W-Re alloys from atomistic calculations. In particular, a virtual specimen is prepared to directly be compared with thin-film experiments. The virtual specimen measures 370 nm in thickness with 6 billion atoms. We will try to explain a governing relation of the grain boundary effects on irradiate damages. |
Proceedings Inclusion? |
Planned: |