In predicting the void fraction in subcooled flow boiling, accurate evaluation of single bubble behaviors is of considerable importance. In particular, bubble lift-off velocity affects the void fraction significantly since the bubble disappear quickly due to heat transfer with subcooled liquid if the lift-off velocity is high. In this study, the process of bubble lift-off was experimentally investigated to develop mechanistic correlations for the bubble lift-off velocity. In the development of the correlations, it was assumed that the bubble lift-off velocity in the horizontal direction is proportional to the bubble growth rate and that in the vertical direction is determined primarily by the local liquid velocity evaluated at the bubble center position. Then, impact of the bubble lift-off velocity on the void fraction was explored through numerical simulations. In the simulations, the bubble lift-off velocity in the lateral direction was parametrically changed. It was shown that the mean void fraction decreases with an increase in the lateral bubble lift-off velocity since the bubble condensation is enhanced. It was therefore confirmed that accurate evaluation of the bubble lift-off velocity is important for high accuracy prediction of the void fraction.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5153-1
PROCEEDINGS PAPER
Modeling of Bubble Behavior in Low Void Fraction Subcooled Flow Boiling
Shintaro Sakamoto,
Shintaro Sakamoto
University of Electro-Communications, Chofu City, Japan
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Hiroki Ohori,
Hiroki Ohori
University of Electro-Communications, Chofu City, Japan
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Koji Enoki,
Koji Enoki
University of Electro-Communications, Chofu City, Japan
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Tomio Okawa
Tomio Okawa
University of Electro-Communications, Chofu City, Japan
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Shintaro Sakamoto
University of Electro-Communications, Chofu City, Japan
Hiroki Ohori
University of Electro-Communications, Chofu City, Japan
Koji Enoki
University of Electro-Communications, Chofu City, Japan
Tomio Okawa
University of Electro-Communications, Chofu City, Japan
Paper No:
ICONE26-81173, V009T16A010; 7 pages
Published Online:
October 24, 2018
Citation
Sakamoto, S, Ohori, H, Enoki, K, & Okawa, T. "Modeling of Bubble Behavior in Low Void Fraction Subcooled Flow Boiling." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 9: Student Paper Competition. London, England. July 22–26, 2018. V009T16A010. ASME. https://doi.org/10.1115/ICONE26-81173
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