Convective Boiling in Narrow Concentric Annuli

[+] Author and Article Information
S. G. Bankoff, T. E. Rehm

Department of Chemical Engineering, Northwestern University, Evanston, IL 60208

J. Eng. Gas Turbines Power 112(4), 607-613 (Oct 01, 1990) (7 pages) doi:10.1115/1.2906213 History: Received August 07, 1987; Revised October 03, 1989; Online April 24, 2008


An experimental apparatus was used to simulate the annulus formed by a single tube passing through a tube support plate (TSP) in the steam generator of a PWR nuclear power plant. It was found that the extent of thin film evaporation, compared to nucleate boiling, is larger for smaller annuli, with a transition at 0.203 mm gap width to a local dryout/rewet condition. A model was developed that predicts an increasing extent of surface dryout/rewet prior to critical heat flux (CHF). A CHF correlation was developed by modification of a pool boiling CHF correlation, and the Chen (1966) correlation was modified to allow prediction of the two-phase heat transfer coefficient.

Copyright © 1990 by The American Society of Mechanical Engineers
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