Air-water CCFL (countercurrent flow limitation) tests using the 1/5th scale rectangular channel and 1/15th scale circular tube simulating a PWR hot leg and both air-water and steam-water CCFL tests using the 1/3rd scale rectangular channel were previously carried out at Kobe University and Forschungszentrum Dresden-Rossendorf (FZD), respectively. In this paper, numerical calculations for the air-water CCFL tests at FZD using FLUENT6.3.26 are presented and compared with the experimental data at Kobe University and FZD. In the calculations, the VOF (volume of fluid) model or two-fluid (2F) model was used. Major results were as follows: (1) the calculated CCFL characteristics using the 2F model for the FZD tests agreed well with the 1/15th scale circular tube data obtained at Kobe University and the calculated results for full-scale PWR conditions, which supported the validity of the 1/3rd scale rectangular channel to simulate CCFL in circular tubes; and (2) comparison with the FZD data showed that the calculations using the 2F and VOF models overestimated the falling water flow rates.
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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
Numerical Calculations for Air-Water Tests on CCFL in Different-Scale Models of a PWR Hot Leg
Michio Murase,
Michio Murase
Institute of Nuclear Safety System, Inc. (INSS), Mihama, Fukui, Japan
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Ikuo Kinoshita,
Ikuo Kinoshita
Institute of Nuclear Safety System, Inc. (INSS), Mihama, Fukui, Japan
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Yoichi Utanohara,
Yoichi Utanohara
Institute of Nuclear Safety System, Inc. (INSS), Mihama, Fukui, Japan
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Dirk Lucas,
Dirk Lucas
Forschungszentrum Dresden-Rossendorf e. V. (FZD), Dresden, Germany
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Christophe Valle´e,
Christophe Valle´e
Forschungszentrum Dresden-Rossendorf e. V. (FZD), Dresden, Germany
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Akio Tomiyama
Akio Tomiyama
Kobe University, Kobe, Hyogo, Japan
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Michio Murase
Institute of Nuclear Safety System, Inc. (INSS), Mihama, Fukui, Japan
Ikuo Kinoshita
Institute of Nuclear Safety System, Inc. (INSS), Mihama, Fukui, Japan
Yoichi Utanohara
Institute of Nuclear Safety System, Inc. (INSS), Mihama, Fukui, Japan
Dirk Lucas
Forschungszentrum Dresden-Rossendorf e. V. (FZD), Dresden, Germany
Christophe Valle´e
Forschungszentrum Dresden-Rossendorf e. V. (FZD), Dresden, Germany
Akio Tomiyama
Kobe University, Kobe, Hyogo, Japan
Paper No:
ICONE18-29092, pp. 123-131; 9 pages
Published Online:
April 8, 2011
Citation
Murase, M, Kinoshita, I, Utanohara, Y, Lucas, D, Valle´e, C, & Tomiyama, A. "Numerical Calculations for Air-Water Tests on CCFL in Different-Scale Models of a PWR Hot Leg." 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. 123-131. ASME. https://doi.org/10.1115/ICONE18-29092
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