Journal article
Heat transfer effectiveness for cooling of Canadian SCWR fuel assembly under the LOCA/LOECC scenario
Abstract
The effectiveness of heat transfer from the fuel rods to the moderator in a Canadian, pressure-tube type, Super-Critical Water-cooled Reactor (SCWR) has been assessed for the postulated loss-of-coolant accident (LOCA) coupled with the total loss of emergency core cooling (LOECC) event using the safety analysis code “SCTRAN”. A radiation heat-transfer model, including a two-dimensional heat conduction solution scheme, has been incorporated into …
Authors
Wu P; Shan J; Gou J; Leung LKH; Zhang B; Zhang B
Journal
Annals of Nuclear Energy, Vol. 81, , pp. 306–319
Publisher
Elsevier
Publication Date
July 2015
DOI
10.1016/j.anucene.2015.03.006
ISSN
0306-4549