The effect of heated length on critical heat flux (CHF) in thin rectangular channels under atmospheric pressure has been studied. CHF in small channels has been widely studied in the last decades but most of the studies are based on flow in round tubes and number of studies focused on rectangular channels is relatively small. Although basic triggering mechanisms, which lead to CHF in thin rectangular channels, are similar to that of tubes, applicability of thermal hydraulic correlations developed for tubes to rectangular channels are questionable since heat transfer in rectangular channels are affected by the existence of nonheated walls and the noncircular geometry of channel circumference. Several studies of CHF in thin rectangular channels have been reported in relation to thermal hydraulic design of research reactors and neutron source targets and correlations have been proposed, but the studies mostly focus on geometrical conditions of the application of interest and therefore effect of channel parameters exceeding their interest is not fully understood. In his study, CHF data for thin rectangular channels have been collected from previous studies and the effect of heated length on CHF was examined. Existing correlations were verified with data with positive quality outlet flow but none of the correlations successfully reproduced the data for a wide range of heated lengths. A new CHF correlation for quality region applicable to a wide range of heated lengths has been developed based on the collected data.
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e-mail: f_tanaka@mhi.co.jp
e-mail: hibiki@ecn.purdue.edu
e-mail: mishima@rri.kyoto-u.ac.jp; mishima.kaichiro@inss.co.jp
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December 2009
This article was originally published in
Journal of Heat Transfer
Research Papers
Correlation for Flow Boiling Critical Heat Flux in Thin Rectangular Channels
Futoshi Tanaka,
Futoshi Tanaka
Graduate School of Energy Science,
e-mail: f_tanaka@mhi.co.jp
Kyoto University
; and Mitsubishi Heavy Industries, LTD.
, 16-5, Konan 2-Chome, Minato-ku, Tokyo 108-8215, Japan
Search for other works by this author on:
Takashi Hibiki,
Takashi Hibiki
School of Nuclear Engineering,
e-mail: hibiki@ecn.purdue.edu
Purdue University
, Nuclear Engineering Building, Room 132C, 400 Central Drive, West Lafayette, IN 47907-2017
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Kaichiro Mishima
Kaichiro Mishima
Research Reactor Institute,
e-mail: mishima@rri.kyoto-u.ac.jp; mishima.kaichiro@inss.co.jp
Kyoto University
, Kumatori, Sennan, Osaka 590-0494, Japan
; and Institute of Nuclear Safety System, Incorporated, 64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205 Japan
Search for other works by this author on:
Futoshi Tanaka
Graduate School of Energy Science,
Kyoto University
; and Mitsubishi Heavy Industries, LTD.
, 16-5, Konan 2-Chome, Minato-ku, Tokyo 108-8215, Japane-mail: f_tanaka@mhi.co.jp
Takashi Hibiki
School of Nuclear Engineering,
Purdue University
, Nuclear Engineering Building, Room 132C, 400 Central Drive, West Lafayette, IN 47907-2017e-mail: hibiki@ecn.purdue.edu
Kaichiro Mishima
Research Reactor Institute,
Kyoto University
, Kumatori, Sennan, Osaka 590-0494, Japan
; and Institute of Nuclear Safety System, Incorporated, 64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205 Japane-mail: mishima@rri.kyoto-u.ac.jp; mishima.kaichiro@inss.co.jp
J. Heat Transfer. Dec 2009, 131(12): 121003 (7 pages)
Published Online: October 15, 2009
Article history
Received:
September 11, 2007
Revised:
December 22, 2008
Published:
October 15, 2009
Citation
Tanaka, F., Hibiki, T., and Mishima, K. (October 15, 2009). "Correlation for Flow Boiling Critical Heat Flux in Thin Rectangular Channels." ASME. J. Heat Transfer. December 2009; 131(12): 121003. https://doi.org/10.1115/1.3216037
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