The effect of reduction of input-parameters on data-driven prediction of critical heat flux in rod bundles using extended parameters for reactor thermal–hydraulic safety
Fields of Study & Subjects
Nuclear Engineering Thermal-Hydraulics
Heat transfer and supercritical fluids
Heat Transfer and Boiling Studies
Publication details
- Journal / source
- International Communications in Heat and Mass Transfer
- Publisher
- Elsevier BV
- Volume
- 172
- Pages
- 110659–110659
- Publication date
- 3 February 2026
- Language
- EN