Gas ingestion arises from free surface dip during draining from liquid storage tank does serious damage to the nuclear engineering practices, which should be considered in the design work. In this article, numerical simulations of transient process of draining from cylindrical tanks have been conducted with volume-of-fluid (VOF) method, by using the commercial CFD code FLUENT14.5. The relation between critical submerged depth and the Froude number has been investigated, then the influence of different factors on critical submerged depth also has been discussed. The results show that the Jain’s empirical formula are available to estimate the critical submerged depth flow with weak vortex in the condition of high diameter ratio and high initial water level. Moreover, the initial strong vortex significantly increase the critical submerged depth, while the surface tension has pretty small effects on the critical submerged depth when the Froude number is large.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5004-6
PROCEEDINGS PAPER
Numerical Investigation on Critical Submerged Depth During Draining From Cylindrical Tanks
Liu Shi-wen,
Liu Shi-wen
Nuclear Power Institute of China, Chengdu, China
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Zhou Jie,
Zhou Jie
Nuclear Power Institute of China, Chengdu, China
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Huang Wei,
Huang Wei
Nuclear Power Institute of China, Chengdu, China
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Cheng Xiang
Cheng Xiang
Nuclear Power Institute of China, Chengdu, China
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Liu Shi-wen
Nuclear Power Institute of China, Chengdu, China
Zhou Jie
Nuclear Power Institute of China, Chengdu, China
Huang Wei
Nuclear Power Institute of China, Chengdu, China
Cheng Xiang
Nuclear Power Institute of China, Chengdu, China
Paper No:
ICONE24-60376, V004T10A015; 6 pages
Published Online:
October 25, 2016
Citation
Shi-wen, L, Jie, Z, Wei, H, & Xiang, C. "Numerical Investigation on Critical Submerged Depth During Draining From Cylindrical Tanks." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management. Charlotte, North Carolina, USA. June 26–30, 2016. V004T10A015. ASME. https://doi.org/10.1115/ICONE24-60376
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