View in EDS

Thermal-hydraulic analysis of a representative Westinghouse lead-cooled fast reactor fuel bundle using CFD.

Saved in:
Bibliographic Details
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
Be the first to leave a comment!
You must be logged in first