Oxygen Corrosion Simulation of Lead Cooled Fast Reactor SNCLFR-100 Based on Nuclear Thermal Coupling Program
Fields of Study & Subjects
Nuclear reactor physics and engineering
Nuclear Engineering Thermal-Hydraulics
Nuclear Materials and Properties
Publication details
- Journal / source
- Springer proceedings in physics
- Pages
- 319–331
- Publication date
- 1 January 2026
- Language
- EN