Numerical investigation of buoyancy effect on forced convective heat transfer to supercritical carbon dioxide flowing in a vertical tube was carried out. When the mass flux is low and wall heat flux high, it shows that the buoyancy effect is obvious, which might redistribute the radial and axial velocity, even M shaped distribution in the radial direction. When the zero-velocity-gradient region corresponding to the M shaped velocity distribution appears in the edge of viscous layer, the production and diffusion of eddy will be weakened, resulting in heat transfer deterioration. According to the extended simulations based on experimental data, reducing the wall heat flux, adding the mass flux or raising the inlet temperature can relieve the deterioration of heat transfer caused by buoyancy effect.
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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
Numerical Investigation of Buoyancy Effect on Forced Convective Heat Transfer to Supercritical Carbon Dioxide Flowing in a Heated Tube
Liu Sheng-hui,
Liu Sheng-hui
Nuclear Power Institute of China, Chengdu, China
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Huang Yan-ping,
Huang Yan-ping
Nuclear Power Institute of China, Chengdu, China
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Liu Guang-xu,
Liu Guang-xu
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Wang Jun-feng
Wang Jun-feng
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Liu Sheng-hui
Nuclear Power Institute of China, Chengdu, China
Huang Yan-ping
Nuclear Power Institute of China, Chengdu, China
Liu Guang-xu
Nuclear Power Institute of China, Chengdu, China
Wang Jun-feng
Nuclear Power Institute of China, Chengdu, China
Paper No:
ICONE26-81450, V06AT08A040; 6 pages
Published Online:
October 24, 2018
Citation
Sheng-hui, L, Yan-ping, H, Guang-xu, L, & Jun-feng, W. "Numerical Investigation of Buoyancy Effect on Forced Convective Heat Transfer to Supercritical Carbon Dioxide Flowing in a Heated Tube." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 6A: Thermal-Hydraulics and Safety Analyses. London, England. July 22–26, 2018. V06AT08A040. ASME. https://doi.org/10.1115/ICONE26-81450
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