
Methodology for thermal analysis of spent nuclear fuel dry cask using CFD codes
Benavides, Julio, Jimenez, Gonzalo, Galbán, Marta, Lloret, MiriamVolume:
133
Langue:
english
Journal:
Annals of Nuclear Energy
DOI:
10.1016/j.anucene.2019.05.026
Date:
November, 2019
Fichier:
PDF, 5.71 MB
english, 2019