About
Contact & Profiles
Research Areas
- Advanced materials and composites
- Advanced ceramic materials synthesis
- Diamond and Carbon-based Materials Research
- Aluminum Alloys Composites Properties
- Silicon Carbide Semiconductor Technologies
- Metal and Thin Film Mechanics
- Fusion materials and technologies
- High-Temperature Coating Behaviors
- Semiconductor materials and devices
- High Entropy Alloys Studies
- Nuclear Materials and Properties
Shanghai Ocean University
2024-2025
Tohoku University
2022-2023
10.1007/s40195-024-01804-y
article
EN
Acta Metallurgica Sinica (English Letters)
2025-01-04
10.1016/j.ceramint.2025.01.121
article
EN
Ceramics International
2025-01-01
10.1016/j.jeurceramsoc.2024.04.064
article
EN
Journal of the European Ceramic Society
2024-05-02
10.1016/j.jeurceramsoc.2023.04.042
article
EN
Journal of the European Ceramic Society
2023-04-20
10.1016/j.jeurceramsoc.2022.06.051
article
EN
publisher-specific-oa
Journal of the European Ceramic Society
2022-06-18
Oxide dispersion-strengthened (ODS) steels are promising candidates for constructing nuclear reactors. Considering a high-temperature environment, ODS austenitic could provide superior performance compared to the current ferritic steels. To meet reduced activation requirement, compositions of have be carefully adjust. Currently, authors focus on with austenite stabilizer Mn, and several amounts Al added improve their oxidation resistance. This study investigates third-element effects Cr Si...
10.1016/j.nme.2023.101572
article
EN
cc-by-nc-nd
Nuclear Materials and Energy
2023-12-21
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