Evolution of fatigue-induced cracks in Cr-coated Zr alloy cladding in high-temperature steam environment
Fields of Study & Subjects
Nuclear Materials and Properties
Nuclear Engineering Thermal-Hydraulics
Fusion materials and technologies
Publication details
- Journal / source
- Corrosion Science
- Publisher
- Elsevier BV
- Volume
- 263
- Pages
- 113722–113722
- Publication date
- 21 February 2026
- Language
- EN