Numerical simulation code for predicting void distribution in two-phase turbulent flow in a sub-channel was developed. The purpose is to obtain a profile of void distribution in the sub-channel. The result will be used for predicting a heat flux at departure from nucleate boiling (DNB) in a rod bundle for the pressurized water reactor (PWR). The fundamental equations were represented by a generalized transport equation, and the transport equation was transformed onto the generalized coordinate system fitted to the rod surface and the symmetric lines in the sub-channel. Using the finite-volume method the transport equation was discretized for the SIMPLE algorism. The flow field and void fraction at the steady state were calculated for different average void fractions. The computational result for atmospheric pressure condition was successfully compared with experimental data. Sensitivity analysis for the PWR condition was performed, and the result showed that the secondary flow slightly contributed to homogenizing the void distribution.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4355-0
PROCEEDINGS PAPER
Numerical Prediction of Void Distribution in Two-Phase Turbulent Flow in a Sub-Channel
Tsutomu Ikeno,
Tsutomu Ikeno
Nuclear Fuel Industries, Ltd., Kumatori, Osaka, Japan
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Tatsuya Sasakawa,
Tatsuya Sasakawa
Nuclear Fuel Industries, Ltd., Kumatori, Osaka, Japan
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Isao Kataoka
Isao Kataoka
Osaka University, Suita, Osaka, Japan
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Tsutomu Ikeno
Nuclear Fuel Industries, Ltd., Kumatori, Osaka, Japan
Tatsuya Sasakawa
Nuclear Fuel Industries, Ltd., Kumatori, Osaka, Japan
Isao Kataoka
Osaka University, Suita, Osaka, Japan
Paper No:
ICONE17-75302, pp. 327-334; 8 pages
Published Online:
February 25, 2010
Citation
Ikeno, T, Sasakawa, T, & Kataoka, I. "Numerical Prediction of Void Distribution in Two-Phase Turbulent Flow in a Sub-Channel." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control. Brussels, Belgium. July 12–16, 2009. pp. 327-334. ASME. https://doi.org/10.1115/ICONE17-75302
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