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Multiphase Science and Technology
SJR: 0.124 SNIP: 0.222 CiteScore™: 0.26

ISSN Imprimir: 0276-1459
ISSN On-line: 1943-6181

Multiphase Science and Technology

DOI: 10.1615/MultScienTechn.v22.i2.20
pages 115-132

FLOW BOILING IN HORIZONTAL MINICHANNELS: FLOW PATTERN OF CO2 AT HIGH PRESSURE

Mamoru Ozawa
Department of Safety Science, Kansai University, 7-1 Hakubai-cho, Takatsuki-shi, Osaka 569-1098, Japan
Hisashi Umekawa
Department of Mechanical Engineering, Kansai University, 3-3-35 Yamate-cho, Suita-shi, Osaka 564-8680, Japan
T. Ami
Kansai University, Suita, Osaka
Ryosuke Matsumoto
Department of Mechanical Systems Engineering Kansai University, 3-3-35 Yamate-cyo, Suita, Osaka 564-8680
T. Hara
Department of Mechanical Engineering, Kansai University, Suita, Osaka 564-8680

RESUMO

This paper describes the flow patterns of carbon dioxide two-phase flow at high pressure observed in horizontal minichannels ranging from 0.51 to 3.0 mm in diameter, together with the flow pattern maps and related boiling heat-transfer characteristics. The observed flow patterns are mainly classified into bubbly, slug, slug-annular, and annular flows, similar to conventional pipes, while phase stratification tendency is still significant even in a 1.0 mm tube, so that heat transfer at high pressure shows significant differences in the upper and lower walls, especially in 2.0 and 3.0 mm tubes. Such phase stratification with reference to heat transfer is roughly scaled by means of boiling number and Bond number. The newly developed simulation model by the authors for conventional-sized tubes is successfully applied to 2.0 and 3.0 mm pipes, but not to 0.51 and 1.0 mm tubes. This model suggests that thermal flow behavior at higher Bond number Bo than 8.2 is similar to that of conventional-sized tube, and cases less than Bo = 8.2 show minichannel behavior. The heat transfer in these minichannels is well-predicted with Schrock{Grossman type correlation with nucleate and forced-convective effects, while in larger tubes, e.g., 2.0 and 3.0 mm, the heat transfer is mainly dominated by nucleate boiling in the present experimental ranges.

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