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Measurements of critical heat flux in CANDU...
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

February 2010

DOI

10.1016/j.nucengdes.2009.09.016

ISSN

0029-5493