Nanofluid has been attracted great attention since it was proposed as a preeminent working fluid. Flow boiling is familiar in heat transfer system and the critical heat flux is a key parameter for the design of thermal hydraulic. In present work, the critical heat flux of nanofluid flow boiling is experimentally investigated in a vertical tube with the consideration of outlet pressure, mass flux, inlet subcooling, heating length and diameter. The results indicate that the critical heat flux of nanofluid flow boiling is enhanced compared with base fluid and the increasing radio is increased with increasing the mass flux, diameter and pressure, and with decreasing the heating length. In addition, the inlet subcooling and concentrations (0.1vol.%, 0.5vol.%) have almost no significant influence. Furthermore, a new mechanism for the enhancement of nanofluid flow boiling critical heat flux was proposed by the SEM images of nanopariticle deposition on the heating surface.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5148-7
PROCEEDINGS PAPER
Experimental Study on the Critical Heat Flux of Nanofluid Flow Boiling Under Different Conditions
Y. Wang,
Y. Wang
Nuclear Power Institute of China, Chengdu, China
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K. H. Deng,
K. H. Deng
Xi'an Jiaotong University, Xi'an, China
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J. M. Wu,
J. M. Wu
Xi'an Jiaotong University, Xi'an, China
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N. N. Yue,
N. N. Yue
Nuclear Power Institute of China, Chengdu, China
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Y. F. Zan,
Y. F. Zan
Nuclear Power Institute of China, Chengdu, China
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G. H. Su,
G. H. Su
Xi'an Jiaotong University, Xi'an, China
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S. Z. Qiu
S. Z. Qiu
Xi'an Jiaotong University, Xi'an, China
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Y. Wang
Nuclear Power Institute of China, Chengdu, China
K. H. Deng
Xi'an Jiaotong University, Xi'an, China
J. M. Wu
Xi'an Jiaotong University, Xi'an, China
N. N. Yue
Nuclear Power Institute of China, Chengdu, China
Y. F. Zan
Nuclear Power Institute of China, Chengdu, China
G. H. Su
Xi'an Jiaotong University, Xi'an, China
S. Z. Qiu
Xi'an Jiaotong University, Xi'an, China
Paper No:
ICONE26-81752, V06AT08A070; 6 pages
Published Online:
October 24, 2018
Citation
Wang, Y, Deng, KH, Wu, JM, Yue, NN, Zan, YF, Su, GH, & Qiu, SZ. "Experimental Study on the Critical Heat Flux of Nanofluid Flow Boiling Under Different Conditions." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 6A: Thermal-Hydraulics and Safety Analyses. London, England. July 22–26, 2018. V06AT08A070. ASME. https://doi.org/10.1115/ICONE26-81752
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