In the present research, a visual experiment was carried out on the flow regimes of the porous channels in the spherical fuel element nuclear reactor. Boiling two-phase flow in different porous channels composed of particles with diameters of 4mm, 6mm and 8mm were studied respectively, and four different flow regimes occur within the experimental parameter range: bubbly flow, bubbly-slug flow, slug flow and slug-annular flow. The effects of heat flux, mass flux and particle diameter on the flow regimes were obtained. Bubbles and slugs deform, coalesce and break up more frequently, and increase in both number and size with the increase of the heat flux; bubbles and slugs tend to decrease in number and size with higher mass flux and particles of smaller diameters. At higher mass flux, a higher heat flux is needed to get the same flow regime that occurs at lower mass flux; with particles of smaller diameter, a higher heat flux is needed to get the same flow regime as that of particles of larger diameter. The flow regime map and flow regime transition have been proposed by modifying the void fractions of Tung/Dhir model.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4353-6
PROCEEDINGS PAPER
Flow Regime Classification and Transition of Flow Boiling Through Porous Channel
Bofeng Bai,
Bofeng Bai
Xi’an Jiaotong University, Xi’an, China
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Xiaojie Zhang,
Xiaojie Zhang
Xi’an Jiaotong University, Xi’an, China
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Maolong Liu,
Maolong Liu
Xi’an Jiaotong University, Xi’an, China
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Wang Su
Wang Su
Xi’an Jiaotong University, Xi’an, China
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Bofeng Bai
Xi’an Jiaotong University, Xi’an, China
Xiaojie Zhang
Xi’an Jiaotong University, Xi’an, China
Maolong Liu
Xi’an Jiaotong University, Xi’an, China
Wang Su
Xi’an Jiaotong University, Xi’an, China
Paper No:
ICONE17-75589, pp. 487-493; 7 pages
Published Online:
February 25, 2010
Citation
Bai, B, Zhang, X, Liu, M, & Su, W. "Flow Regime Classification and Transition of Flow Boiling Through Porous Channel." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance. Brussels, Belgium. July 12–16, 2009. pp. 487-493. ASME. https://doi.org/10.1115/ICONE17-75589
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