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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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The characteristics and visualization of critical heat flux of R-134a flowing in a vertical annular geometry with spacer grids

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Title
The characteristics and visualization of critical heat flux of R-134a flowing in a vertical annular geometry with spacer grids
Author
Lee, Kwi LimBang, In CheolChang, Soon Heung
Issue Date
2008-01
Publisher
PERGAMON-ELSEVIER SCIENCE LTD
Citation
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.51, no.1-2, pp.91 - 103
Abstract
In the present paper, critical heat flux (CHF) experiments of forced convection boiling were performed to investigate the CHF characteristics of a vertical annular channel with one heated rod and four spacer grids for new refrigerant R-134a. The experiments were conducted under outlet pressure of 11.6, 13, 16 and 20 bar, mass fluxes of 100-600 kg/m2 s, and inlet temperatures of 25-40 °C. The parametric trend of the CHF data was well consistent with previous understanding in water. The comparison between the present results with effect of the flow obstacle enhancing CHF and water data in similar geometry shows R-134a can be a modeling fluid for simulating water CHF in high pressure and high temperature condition even for annular geometry. The direct observation of flowing bubble behaviors contributes to enhancing our understanding on the effect of flow obstacles for flow boiling heat transfer.
URI
https://scholarworks.unist.ac.kr/handle/201301/7242
URL
http://www.scopus.com/inward/record.url?partnerID=HzOxMe3b&scp=36849029893
DOI
10.1016/j.ijheatmasstransfer.2007.04.024
ISSN
0017-9310
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