Xinwei Yuan

ORCID: 0009-0005-7709-1304
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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

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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