Conference
Preliminary Investigation of Heat-Transfer Correlation for Upward Flow of CO2 at Supercritical Pressure
Abstract
The development of Generation IV nuclear reactors is an ongoing worldwide interdisciplinary effort. Canada is involved with the development of the SuperCritical Water-cooled Reactor (SCWR). One of the numerous engineering challenges associated with this development is to ensure intensive and stable heat transfer to SuperCritical Water (SCW) in a core. It is very important to develop sophisticated theoretical models to improving understanding of …
Authors
Saltanov E; Pioro I; Harvel G
Pagination
pp. v006t16a037-v006t16a037
Publisher
ASME International
Publication Date
July 29, 2013
DOI
10.1115/icone21-16399
Name of conference
Volume 6: Beyond Design Basis Events; Student Paper Competition