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Bang, In Cheol
Nuclear Thermal-Hydraulics & Reactor Safety Lab
Research Interests
  • Nuclear Thermal-Hydraulics
  • Nuclear Safety
  • Nuclear System Design & Analysis
  • Nanofluids
  • Critical Heat Flux

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Visualization of the subcooled flow boiling of R-134a in a vertical rectangular channel with an electrically heated wall

Cited 17 times inthomson ciCited 18 times inthomson ci
Title
Visualization of the subcooled flow boiling of R-134a in a vertical rectangular channel with an electrically heated wall
Author
Bang, In CheolChang, SHBaek, WP
Keywords
Bubble coalescence; CHF; Near-wall region; R-134a; Visualization
Issue Date
2004-09
Publisher
PERGAMON-ELSEVIER SCIENCE LTD
Citation
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.47, no.19-20, pp.4349 - 4363
Abstract
A digital photographic study of subcooled flow boiling with R-134a was performed in a vertical rectangular channel heated from one side to observe near-wall structures. Primary attention was given to bubble formation and bubble coalescence in the bubble layer. The visualization made possible a detailed observation of the characteristic near-wall region, consisting of vapor remnants, an interleaved liquid layer, and coalesced adjacent bubbles. In particular, the visualization provided clearer insights about bubble coalescence behaviors during flow nucleate boiling. In addition, it is shown that the near-wall bubble layer of nucleate boiling beneath vapor clots is extinguished and, afterwards, the heated surface is locally covered by large vapor films, at CHF.
URI
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DOI
10.1016/j.ijheatmasstransfer.2004.04.030
ISSN
0017-9310
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