Thermal-hydraulic analysis of a representative Westinghouse lead-cooled fast reactor fuel bundle using CFD.
Saved in:
| Title: | Thermal-hydraulic analysis of a representative Westinghouse lead-cooled fast reactor fuel bundle using CFD. |
|---|---|
| Authors: | Wilson, D.1, dean.wilson@manchester.ac.uk, Iacovides, H.1, Tatli, E.2,3, Stansbury, C.2, Ferroni, P.2 |
| Source: | Nuclear Engineering & Design; Aug2025, Vol. 439, pN.PAG-N.PAG, 1p |
| Database: | Applied Science & Technology Source |
| ISSN: | 00295493 |
|---|---|
| DOI: | 10.1016/j.nucengdes.2025.114117 |