The influence of particle introduction into a subcooled water flow on boiling heat transfer and critical heat flux (CHF) was examined. When the water velocity was low, the particles crowded on the bottom wall of the flow channel and flowed just like sliding on the wall. When the water velocity was high, the particles were well dispersed in the water flow. In the non-boiling region, the heat transfer was augmented by the introduction of the particles into the water flow. As the introduction of the particles were increased, the augmentation was also increased in the high water flow rate region. However, it was independent upon the particle introduction rate in the low water flow rate region. The onset of boiling was delayed by the particle inclusion. The boiling heat transfer was enhanced by the particles. However, it was rather decreased in the high heat flux fully-developed-boiling region. The CHF was decreased by the particle inclusion in the low water flow region and was not affected in the high water flow region.
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10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3597-9
PROCEEDINGS PAPER
Study on Enhancement of Sub-Cooled Flow Boiling Heat Transfer and Critical Heat Flux of Solid-Water Two-Phase Mixture
Yasuo Koizumi,
Yasuo Koizumi
Kogakuin University, Hachioji, Tokyo, Japan
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Tomoyuki Suzuki,
Tomoyuki Suzuki
Yokokawa Johnson Controls Company, Tokyo, Japan
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Hiroyasu Ohtake
Hiroyasu Ohtake
Kogakuin University, Hachioji, Tokyo, Japan
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Yasuo Koizumi
Kogakuin University, Hachioji, Tokyo, Japan
Tomoyuki Suzuki
Yokokawa Johnson Controls Company, Tokyo, Japan
Hiroyasu Ohtake
Kogakuin University, Hachioji, Tokyo, Japan
Paper No:
ICONE10-22470, pp. 817-822; 6 pages
Published Online:
March 4, 2009
Citation
Koizumi, Y, Suzuki, T, & Ohtake, H. "Study on Enhancement of Sub-Cooled Flow Boiling Heat Transfer and Critical Heat Flux of Solid-Water Two-Phase Mixture." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 14–18, 2002. pp. 817-822. ASME. https://doi.org/10.1115/ICONE10-22470
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