The near-wall bubble congregating in vertical tube upward flow exerts an influence on fluid heat transfer. A 0.5m test section is simulated using CFX10.0 to research the bubble influence on the heat transfer. The vapor-water two-phase CFD calculation is done. The bubbles are added at near wall area, taking no account of the mass transfer between water and vapor. The different bubble max diameter and the different MUSIG model size group get different calculation results, these results are compared, include the distribution of vapor void fraction, the wall temperature distribution and near-wall water temperature distribution, the bubble mean diameter. A guide setting is advised. The calculation result shows that the max bubble diameter and the MUSIG size group on the vapor void fraction distribution is large. The near-wall void fraction gets down to the least (nearly zero, while at the inlet, near wall vapor fraction is 0.95) at 0.1m∼0.14m axis height, then rises. The wall temperature gets highest at the same height, and then appears a flat, keeping this temperature about 0.1m long, after that the temperature gets down, then rises along the axis.
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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
Bubble Size and Group Influence for CFD Simulation in Vertical Tube Upward Flow
Songwei Li,
Songwei Li
Tsinghua University; Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Hong Zhang
Hong Zhang
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Songwei Li
Tsinghua University; Nuclear Power Institute of China, Chengdu, China
Hong Zhang
Nuclear Power Institute of China, Chengdu, China
Paper No:
ICONE18-30081, pp. 1023-1030; 8 pages
Published Online:
April 8, 2011
Citation
Li, S, & Zhang, H. "Bubble Size and Group Influence for CFD Simulation in Vertical Tube Upward Flow." 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. 1023-1030. ASME. https://doi.org/10.1115/ICONE18-30081
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