In this paper, results of experiments and numerical simulations for counter-current flow in a pressurized water reactor hot leg under reflux cooling are summarized. In the experiments, we used two types of small scale PWR hot legs. One was a 1/5th scale rectangular duct, and the other was a 1/15th scale circular pipe. Air and water were used for gas and liquid phases. The air flow rate and the supplied water flow rate were varied to observe flow pattern and measure the counter-current flow limitation (CCFL) characteristics. Flow patterns in the elbow and the inclined section were strongly affected by those in the horizontal section. In the 1/15th scale circular pipe experiments, CCFL characteristics obtained by increasing the air flow rate differed from those obtained by decreasing it. CCFL characteristics corresponded to the flow pattern transition. In the numerical simulations, we used a three-dimensional two-fluid model to evaluate the capability of predicting counter-current flow in the hot leg. Good agreements between measured and predicted flow patterns and CCFL characteristics were obtained by using an appropriate set of correlations for interfacial friction coefficient. We also carried out simulations of actual hot leg conditions to examine the effects of fluid properties and size. Predicted flow patterns and CCFL characteristics were close to those of scale model calculations. We concluded the combination of calculation model and interfacial friction coefficients used in this study can predict the counter-current flow in a hot leg.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4932-3
PROCEEDINGS PAPER
Study on Countercurrent Flow in a PWR Hot Leg Under Reflux Cooling
Noritoshi Minami,
Noritoshi Minami
Institute of Nuclear Safety System, Inc., Mihama, Fukui, Japan
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Michio Murase,
Michio Murase
Institute of Nuclear Safety System, Inc., Mihama, Fukui, Japan
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Akio Tomiyama
Akio Tomiyama
Kobe University, Kobe, Hyogo, Japan
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Noritoshi Minami
Institute of Nuclear Safety System, Inc., Mihama, Fukui, Japan
Michio Murase
Institute of Nuclear Safety System, Inc., Mihama, Fukui, Japan
Akio Tomiyama
Kobe University, Kobe, Hyogo, Japan
Paper No:
ICONE18-30026, pp. 963-973; 11 pages
Published Online:
April 8, 2011
Citation
Minami, N, Murase, M, & Tomiyama, A. "Study on Countercurrent Flow in a PWR Hot Leg Under Reflux Cooling." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B. Xi’an, China. May 17–21, 2010. pp. 963-973. ASME. https://doi.org/10.1115/ICONE18-30026
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