Critical Heat Flux Modeling in Forced Convection Boiling During Power Transients

[+] Author and Article Information
K. O. Pasamehmetoglu, R. A. Nelson

Nuclear Technology and Engineering Division, Los Alamos National Laboratory, Los Alamos, NM 87545

F. S. Gunnerson

College of Engineering, University of Central Florida, Orlando, FL 32816

J. Heat Transfer 112(4), 1058-1062 (Nov 01, 1990) (5 pages) doi:10.1115/1.2910478 History: Received May 09, 1988; Revised March 16, 1990; Online May 23, 2008


In this paper, a theoretical prediction of critical heat flux (CHF) during power transients in forced convective boiling is presented. The analysis is restricted to departure from nucleate boiling (DNB) type of CHF at low qualities. The developed theory is compared with the experimental data available in the literature. The agreement is exceptionally good. The new model also is compared with the semi-empirical transient CHF model in the literature.

Copyright © 1990 by The American Society of Mechanical Engineers
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