Two fluid model integrating a set of closure relationships (such as inter-phase heat transfer model, inter-phase mass transfer model, inter-phase momentum transfer model, mean bubble diameter model, bubble departure diameter model, bubble departure frequency model, onset of nucleate boiling model, wall heat flux partition model) are applied to solve the local flow and heat transfer of subcooled flow boiling under low pressure, and local flow parameters such as volume fraction, liquid velocity, vapor phase etc. are obtained using developed code. The subcooled flow boiling results predicted in this paper are compared to the subcooled flow boiling experimental results of TH Lee etc. in annular channel with inner tube heated uniformly and adiabatic outer tube, and they agree well. The code can also be used to predict the multiphase flow field in power reactor core when the subcooled flow boiling take place and the critical heat flux of Departure Nucleate Boiling (DNB) in reactor core and it is meaningful for reactor core design.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4932-3
PROCEEDINGS PAPER
Investigation of Subcooled Flow Boiling Model Under Low Pressure
Fan Pu
Fan Pu
Shanghai Nuclear Engineering Research and Design Institute, Shanghai, China
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Fan Pu
Shanghai Nuclear Engineering Research and Design Institute, Shanghai, China
Paper No:
ICONE18-29200, pp. 193-204; 12 pages
Published Online:
April 8, 2011
Citation
Pu, F. "Investigation of Subcooled Flow Boiling Model Under Low Pressure." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B. Xi’an, China. May 17–21, 2010. pp. 193-204. ASME. https://doi.org/10.1115/ICONE18-29200
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