Multi-scale modeling of Zircaloy cladding: From mechanistic crystal plasticity to finite element surrogates with scenario-based validation
Fields of Study & Subjects
Nuclear Materials and Properties
High Temperature Alloys and Creep
Nuclear reactor physics and engineering
Publication details
- Journal / source
- Annals of Nuclear Energy
- Volume
- 240
- Pages
- 112681–112681
- Publication date
- 17 August 2026
- Language
- EN