This study investigates the heat transfer characters of a volumetrically-heated melt pool in LWR lower plenum under different top and side boundary conditions. The inconsistency in parameter definitions in Nu-Ra correlations is addressed, and the effect of 2D geometry and crust formation are analyzed. A summary of test conditions of the previous experimental studies are given. The average upwards and downward Nusselt number from LIVE tests in 3D and 2D geometries are compared with each other and with other well-known correlations. The differences of heat flux distribution along the vessel wall are analyzed regarding boundary cooling condition and crust formation. This paper provides some explanations about the discrepant among the exiting heat transfer correlations and recommends most suitable descriptions of melt pool heat transfer under different accident management scenarios.
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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:
978-0-7918-5002-2
PROCEEDINGS PAPER
Review of Experimental Studies on the Heat Transfer Behaviour of Volumetrically-Heated Pool With Different Boundary Conditions and the Influence of Crust Formation
Xiaoyang Gaus-Liu,
Xiaoyang Gaus-Liu
Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen, Germany
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Alexei Miassoedov,
Alexei Miassoedov
Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen, Germany
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Stephan Gabriel
Stephan Gabriel
Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen, Germany
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Xiaoyang Gaus-Liu
Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen, Germany
Alexei Miassoedov
Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen, Germany
Stephan Gabriel
Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen, Germany
Paper No:
ICONE24-60268, V002T07A007; 13 pages
Published Online:
October 25, 2016
Citation
Gaus-Liu, X, Miassoedov, A, & Gabriel, S. "Review of Experimental Studies on the Heat Transfer Behaviour of Volumetrically-Heated Pool With Different Boundary Conditions and the Influence of Crust Formation." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues. Charlotte, North Carolina, USA. June 26–30, 2016. V002T07A007. ASME. https://doi.org/10.1115/ICONE24-60268
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