Fu-Yun Tsai
Education
Ph.D. Nuclear Engineering NC State University 2022
M.S. Nuclear Engineering and Science National Tsing Hua University 2010
B.S. Physics National Taiwan Normal University 2008
Area(s) of Expertise
Researching environmental effects including irradiation, corrosion and high temperature in nuclear reactor materials, conducting pre- and post-characterization on mechanically deformed and ion-irradiated materials based on high entropy alloy composition and iron-based alloys
Publications
- Corrosion sensitivity of 304 stainless steel to KOH vs. LiOH in nuclear pressurized water reactor water chemistry , npj Materials Degradation (2026)
- Effect of Composition on Grain‐Boundary Chemistry and Fracture Behavior in High‐Entropy Carbides , Journal of the American Ceramic Society (2026)
- Solid-State Reactive Processing of Al–Fe 3 O 4 Nanothermites for In Situ Formation of Soft-Magnetic Fe Nanoparticles in an Aluminum Matrix , ACS Materials Au (2026)
- Corrosion sensitivity of nickel-based Alloy Inconel 600 in pressurized water reactor water chemistry: Can KOH replace LiOH? , Corrosion Science (2025)
- Effect of graphene nanoplatelets fraction on the microstructure and mechanical properties of Inconel 718 composites prepared by spark plasma sintering , Materials Science and Engineering A (2025)
- Liquid metal embrittlement during FAST joining of magnesium and galvanized steel , Journal of Magnesium and Alloys (2025)
- Microstructural Evolution and Magnetic Properties of Spark Plasma Sintered Smco5 and Smco5-Fe Composites , SSRN Electronic Journal (2025)
- Microstructure Evolution, mechanical Properties, and biological Response of Ti-Nb-Zr-Ta (TNZT)/hBN metal matrix composites processed via spark plasma sintering (SPS) , Materials & Design (2025)
- Microstructure and mechanical properties of Inconel-GNP reinforced composites: A parametric study on ball milling and spark plasma sintering , Journal of Materials Research and Technology (2025)
- Structure evolution and tin redistribution during oxidation of Zircaloy-4 at 500°C , Journal of Nuclear Materials (2025)