The process of bubble nucleation in subcooled flow boiling was visualized using a high speed camera to show that the bubble size can be significantly different between the nucleation sites. However, the bubble size is usually assumed constant in the numerical simulation of subcooled flow boiling. To explore the effect of the bubble size distribution on the void fraction in subcooled flow boiling, numerical simulations were performed using a bubble tracking method in which the size and position of each bubble are calculated individually using a Lagrangian coordinates. In the present simulation, the void fraction was greater when the bubble size distribution was taken into consideration. Since the bubble tracking method requires many correlations, further improvement is necessary. The present numerical results however indicate that the bubble size distribution should be taken in to consideration to evaluate the void fraction in subcooled flow boiling accurately.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5003-9
PROCEEDINGS PAPER
Numerical Simulation of Subcooled Flow Boiling Using a Bubble Tracking Method Available to Purchase
Tomio Okawa,
Tomio Okawa
University of Electro-Communications, Chofu-shi, Japan
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Naoki Miyano,
Naoki Miyano
University of Electro-Communications, Chofu-shi, Japan
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Kazuhiro Kaiho,
Kazuhiro Kaiho
University of Electro-Communications, Chofu-shi, Japan
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Koji Enoki
Koji Enoki
University of Electro-Communications, Chofu-shi, Japan
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Tomio Okawa
University of Electro-Communications, Chofu-shi, Japan
Naoki Miyano
University of Electro-Communications, Chofu-shi, Japan
Kazuhiro Kaiho
University of Electro-Communications, Chofu-shi, Japan
Koji Enoki
University of Electro-Communications, Chofu-shi, Japan
Paper No:
ICONE24-60088, V003T09A004; 6 pages
Published Online:
October 25, 2016
Citation
Okawa, T, Miyano, N, Kaiho, K, & Enoki, K. "Numerical Simulation of Subcooled Flow Boiling Using a Bubble Tracking Method." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 3: Thermal-Hydraulics. Charlotte, North Carolina, USA. June 26–30, 2016. V003T09A004. ASME. https://doi.org/10.1115/ICONE24-60088
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