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Heat transfer profiles of a vertical, bare,...
Conference

Heat transfer profiles of a vertical, bare, 7-element bundle cooled with supercritical Freon R-12

Abstract

Experimental datasets on simulated fuel bundles are very limited in availability. Supercritical water-cooled nuclear reactors (SCWRs), as one of the six concepts of Generation IV reactors, cannot be designed without such data. Therefore, a preliminary approach using modeling fluids such as carbon dioxide or refrigerants instead of water is practical. One of the supercritical modeling fluids typically used is Freon (R-12) with the critical …

Authors

Richards G; Harvel GD; Pioro IL; Shelegov AS; Kirillov PL

Volume

264

Pagination

pp. 246-256

Publisher

Elsevier

Publication Date

11 2013

DOI

10.1016/j.nucengdes.2013.02.019

Conference proceedings

Nuclear Engineering and Design

ISSN

0029-5493