Journal article
Measurements of critical heat flux in CANDU 37-element bundle with a steep variation in radial power profile
Abstract
An experiment has been performed to obtain dryout power measurements with a 37-element bundle string simulating radial power profiles of high-enriched fuel (which contains slightly higher enrichment than the CANDU fuel and is not the same as the traditional highly enriched uranium) and natural-uranium fuel. The electrically heated bundle string was cooled with Refrigerant-134a and installed vertically inside the test station. Occurrences of CHF …
Authors
Leung LKH; Dimayuga FC
Journal
Nuclear Engineering and Design, Vol. 240, No. 2, pp. 290–298
Publisher
Elsevier
Publication Date
2 2010
DOI
10.1016/j.nucengdes.2009.09.016
ISSN
0029-5493