Development of Validation Matrix of Fuel Assembly Thermal-Hydraulics Sub-channel Analysis Code for Sodium-Cooled Fast Reactors
Fields of Study & Subjects
Nuclear Engineering Thermal-Hydraulics
Nuclear reactor physics and engineering
Heat transfer and supercritical fluids
Publication details
- Journal / source
- Springer proceedings in physics
- Pages
- 647–659
- Publication date
- 1 January 2026
- Language
- EN