Effects of Fe self-ion irradiation on a low carbon MX-ODS steel at 550°C

作者：Yuwen Xu, Di Yun, Yan Xu, Ping Zhang, Wei Yan, Yanfen Li, Chao Li, Lifang Jiao, Tongmin Zhang, Jun Li, Junjun Zhou, Long Kang, Chenyang Lu · 发表于：Frontiers in Energy Research · 年份：2023 · DOI：10.3389/fenrg.2022.988745 · 被引用次数：7 · 研究领域：Fusion materials and technologies、Ion-surface interactions and analysis、Nuclear Materials and Properties

Oxide Dispersion Strengthened (ODS) steels with nano-scale oxides have become one of the candidate materials used in advanced nuclear reactor systems. A novel MX-ODS steel with extremely low carbon content was irradiated with 3 MeV Fe ions at 550°C up to peak damage of 70 dpa. The steel contains uniformly distributed Y 2 O 3 nano-precipitates with an average size of 3.5 nm and a number density of 5 × 10 22 /m 3 . A V-rich shell was found surrounding the core of Y, O, and Si at some particles. Two types of large precipitates, Y-Ta-Si oxides, and VN, were observed in the steel instead of carbides. Voids of very small size are present due to irradiation and the calculated void swelling was only 0.004%, suggesting good irradiation tolerance of the MX-ODS steel in this study. Fine and dense oxide nano-precipitates and their shell-core structure remained stable while the shape of large precipitates changed after irradiation.