Novitrian Novitrian
Nuclear Physics and Biophysics Research Division, Institut Teknologi Bandung

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Evaluation of Pb-Bi-Water Direct Contact Boiling Flow in a Vertical Circular Channel using Drift-Flux Model Novitrian Novitrian; Minoru Takahashi
Indonesian Journal of Physics Vol 19 No 4 (2008): Vol. 19 No. 4, October 2008
Publisher : Institut Teknologi Bandung

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (187.308 KB) | DOI: 10.5614/itb.ijp.2008.19.4.1

Abstract

The characteristics of Pb-Bi-water boiling two-phase flow were investigated in a vertical circular channel. Water was injected into Pb-Bi to circulate Pb-Bi in a loop with an effect of steam lift pump. Pb-Bi flow rates were measured and analytically estimated using balance condition between buoyancy force and pressure losses. The drift-flux model was used to determine void fraction with assumption that bubble sizes were dependent on the fluid surface tension and density ratio of Pb-Bi to steam and water mixture. The result of analysis shows that the deviation from the experimental data was less than 20%.