Onset of nucleate boiling — ONB — and critical heat flux — CHF — on subcooled flow boiling under vibration condition, focusing on liquid velocity, amplitude and frequency of vibration, were investigated experimentally. Experiments were conducted using a copper thin-film and subcooled water in a range of the liquid velocity from 0.27 to 4.07 m/s at 0.10MPa. The liquid subcooling was 20K. The test section was set on a vibration table. The acceleration was 1.3 and 4.2 m/s2, respectively; the frequency was 2, 4 and 20 Hz, respectively. The test section was arranged for horizontal position facing upward and for vertical position, respectively: the vibration directions were horizontal and vertical to orientation of the heater. The present experimental results showed that critical heat fluxes under the vibration conditions of both vibration directions, i.e., horizontal and vertical vibrations to the heater, were higher than those for steady flow. The CHF under the vibration condition was increased with an increasing of acceleration of vibration. According to present observations, coalesced bubble on the heater was frequently released by vibration of the test heater. This behavior causes the CHF to become higher under the vibration condition.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4353-6
PROCEEDINGS PAPER
Study on Subcooled Flow Boiling Heat Transfer Under Vibration Conditions
Hiroyasu Ohtake,
Hiroyasu Ohtake
Kogakuin University, Hachioji, Tokyo, Japan
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Naoki Uchida,
Naoki Uchida
Kogakuin University, Hachioji, Tokyo, Japan
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Yasuo Koizumi
Yasuo Koizumi
Kogakuin University, Hachioji, Tokyo, Japan
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Hiroyasu Ohtake
Kogakuin University, Hachioji, Tokyo, Japan
Naoki Uchida
Kogakuin University, Hachioji, Tokyo, Japan
Yasuo Koizumi
Kogakuin University, Hachioji, Tokyo, Japan
Paper No:
ICONE17-75738, pp. 619-623; 5 pages
Published Online:
February 25, 2010
Citation
Ohtake, H, Uchida, N, & Koizumi, Y. "Study on Subcooled Flow Boiling Heat Transfer Under Vibration Conditions." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance. Brussels, Belgium. July 12–16, 2009. pp. 619-623. ASME. https://doi.org/10.1115/ICONE17-75738
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