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

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

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 uni...

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Bibliographic Details
Main Authors: Yuwen Xu, Di Yun, Xu Yan, Ping Zhang, Wei Yan, Yanfen Li, Chao Li, Jiao Li, Tongmin Zhang, Jun Li, Junjun Zhou, Long Kang, Chenyang Lu
Format: Article
Language:English
Published: Frontiers Media S.A. 2023-01-01
Series:Frontiers in Energy Research
Subjects:
ODS steel
ion irradiation
void swelling
oxide nano-precipitate
MX phase
Online Access:https://www.frontiersin.org/articles/10.3389/fenrg.2022.988745/full

Internet

https://www.frontiersin.org/articles/10.3389/fenrg.2022.988745/full

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