Gas-liquid flow and heat transfer in a nuclear reactor were investigated by the CFD simulation. The MUSIG model and the mono-disperse model are applied to model the multiphase flow and heat transfer. The comparison with experimental data indicates that the gas-liquid flow and heat transfer in the nuclear reactor could be well captured by the suggested numerical model. The temperature distribution, velocity distribution, bubble diameter distribution in the nuclear reactor and heat transfer coefficient of the cooling coils were analyzed. In addition, the effect of gas generation rate on heat transfer coefficient of the cooling coils was discussed. This research work has provided fundamental understanding of gas-liquid flow and heat transfer in the nuclear reactor as well as the design guidance of the cooling coils.
- Heat Transfer Division
Numerical Investigation on Bubbly Flow and Heat Transfer Characters in a Liquid-Reactor
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Yang, L. "Numerical Investigation on Bubbly Flow and Heat Transfer Characters in a Liquid-Reactor." Proceedings of the ASME 2008 Heat Transfer Summer Conference collocated with the Fluids Engineering, Energy Sustainability, and 3rd Energy Nanotechnology Conferences. Heat Transfer: Volume 2. Jacksonville, Florida, USA. August 10–14, 2008. pp. 525-530. ASME. https://doi.org/10.1115/HT2008-56246
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