Bidirectional degradation of the Mo diffusion barrier in FeCrAl-coated Zircaloy-4 during steam oxidation above the Fe-Zr eutectic temperature
Fields of Study & Subjects
Nuclear Materials and Properties
High-Temperature Coating Behaviors
Nuclear reactor physics and engineering
Publication details
- Journal / source
- Corrosion Science
- Publisher
- Elsevier BV
- Volume
- 270
- Pages
- 114074–114074
- Publication date
- 27 June 2026
- Language
- EN