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TECHNICAL BRIEFS

Fully Developed Nucleate Boiling in Narrow Vertical Channels

[+] Author and Article Information
M. S. Lakshminarasimhan, Q. Lu, Y. Chin, D. K. Hollingsworth

Department of Mechanical Engineering,  University of Houston, Houston, TX, 77204-4792

Larry C. Witte

Department of Mechanical Engineering,  University of Houston, Houston, TX, 77204-4792witte@uh.edu

J. Heat Transfer 127(8), 941-944 (Nov 04, 2004) (4 pages) doi:10.1115/1.1928914 History: Received April 12, 2004; Revised November 04, 2004

Experiments were performed to investigate nucleate flow boiling and incipience in a vertical flow channel, 20mmwide×357mmlong, with one wall heated uniformly and others approximately adiabatic. Three channel spacings, 2, 1 and 0.5mm, were investigated. Initially subcooled R-11 flowed upward through the channel; the mass flux varied from 60to4586kg(m2s), and the inlet pressure ranged up to 0.20MPa. Liquid crystal thermography was used to measure distributions of surface temperature from which the heat transfer coefficients on the heated surface were calculated. Fully developed saturated nucleate boiling was correlated well by a modification of Kandlikar’s technique.

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Copyright © 2005 by American Society of Mechanical Engineers
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Figures

Grahic Jump Location
Figure 1

Cross-section views of the channel, (a) longitudinal, (b) transverse with construction detail. For (b) the gravity vector is pointing out of the page.

Grahic Jump Location
Figure 2

The repeatability of two 2mm channel experiments from the same heater and TLC coatings. Run 1: u=1.86m∕s, G=2647kg∕m2s, pi=0.181MPa, ΔTsub,i=8.28°C. Run 2: u=1.86m∕s, G=2663kg∕m2s, pi=0.180MPa, ΔTsub,i=8.23°C.

Grahic Jump Location
Figure 3

Narrow channel data compared to Kandlikar’s correlation

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