One-region (1-R) sensitivity computations with the annular-flow model were carried out for countercurrent flow limitation (CCFL) at a sharp-edged lower end in vertical pipes to generalize the prediction method for CCFL there (i.e., predicting effects of diameters and fluid properties on CCFL characteristics). In our previous study, we selected a correlation of interfacial friction coefficients, fi, with a function of average void fraction which gave a good prediction of the trend for air–water CCFL data, and we modified it to get good agreement with steam–water CCFL data under atmospheric pressure conditions, but it failed to predict CCFL reasonably at high pressure conditions. We recently found a Russian report on CCFL data at high pressure conditions, by which we improved the fi correlation using the dimensionless diameter and the viscosity ratio or density ratio of gas and liquid phases to get good agreement with CCFL data at high pressures. The improved fi correlation with the viscosity ratio and the improved fi correlation with the density ratio gave similar computed results, but the number of adjustment functions was one for the density ratio and two for the viscosity ratio (i.e., minimum value of two functions).
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July 2018
Research-Article
Correlation of Interfacial Friction Coefficients for Predicting Countercurrent Flow Limitation at a Sharp-Edged Lower End of Vertical Pipes
Michio Murase,
Michio Murase
Mem. ASME
Institute of Nuclear Technology,
64 Sata, Mihama-cho, Miata-gun,
Fukui 919-1205, Japan
e-mail: murase@inss.co.jp
Institute of Nuclear Technology,
64 Sata, Mihama-cho, Miata-gun,
Fukui 919-1205, Japan
e-mail: murase@inss.co.jp
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Takayoshi Kusunoki,
Takayoshi Kusunoki
Institute of Nuclear Technology,
64 Sata, Mihama-cho, Mikata-gun,
Fukui 919-1205, Japan
e-mail: kusunoki.takayoshi@inss.co.jp
64 Sata, Mihama-cho, Mikata-gun,
Fukui 919-1205, Japan
e-mail: kusunoki.takayoshi@inss.co.jp
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Koji Nishida,
Koji Nishida
Institute of Nuclear Technology,
64 Sata, Mihama-cho, Mikata-gun,
Fukui 919-1205, Japan
e-mail: nishida.koji@inss.co.jp
64 Sata, Mihama-cho, Mikata-gun,
Fukui 919-1205, Japan
e-mail: nishida.koji@inss.co.jp
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Raito Goda,
Raito Goda
Graduate School of Engineering,
Kobe University,
1-1 Rokkodai, Nada-ku,
Kobe-shi 657-8501, Hyogo, Japan
e-mail: goda@cfrg.scitec.kobe-u.ac.jp
Kobe University,
1-1 Rokkodai, Nada-ku,
Kobe-shi 657-8501, Hyogo, Japan
e-mail: goda@cfrg.scitec.kobe-u.ac.jp
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Akio Tomiyama
Akio Tomiyama
Graduate School of Engineering,
Kobe University,
1-1 Rokkodai, Nada-ku,
Kobe-shi 657-8501, Hyogo, Japan
e-mail: tomiyama@mech.kobe-u.ac.jp
Kobe University,
1-1 Rokkodai, Nada-ku,
Kobe-shi 657-8501, Hyogo, Japan
e-mail: tomiyama@mech.kobe-u.ac.jp
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Michio Murase
Mem. ASME
Institute of Nuclear Technology,
64 Sata, Mihama-cho, Miata-gun,
Fukui 919-1205, Japan
e-mail: murase@inss.co.jp
Institute of Nuclear Technology,
64 Sata, Mihama-cho, Miata-gun,
Fukui 919-1205, Japan
e-mail: murase@inss.co.jp
Takayoshi Kusunoki
Institute of Nuclear Technology,
64 Sata, Mihama-cho, Mikata-gun,
Fukui 919-1205, Japan
e-mail: kusunoki.takayoshi@inss.co.jp
64 Sata, Mihama-cho, Mikata-gun,
Fukui 919-1205, Japan
e-mail: kusunoki.takayoshi@inss.co.jp
Koji Nishida
Institute of Nuclear Technology,
64 Sata, Mihama-cho, Mikata-gun,
Fukui 919-1205, Japan
e-mail: nishida.koji@inss.co.jp
64 Sata, Mihama-cho, Mikata-gun,
Fukui 919-1205, Japan
e-mail: nishida.koji@inss.co.jp
Raito Goda
Graduate School of Engineering,
Kobe University,
1-1 Rokkodai, Nada-ku,
Kobe-shi 657-8501, Hyogo, Japan
e-mail: goda@cfrg.scitec.kobe-u.ac.jp
Kobe University,
1-1 Rokkodai, Nada-ku,
Kobe-shi 657-8501, Hyogo, Japan
e-mail: goda@cfrg.scitec.kobe-u.ac.jp
Akio Tomiyama
Graduate School of Engineering,
Kobe University,
1-1 Rokkodai, Nada-ku,
Kobe-shi 657-8501, Hyogo, Japan
e-mail: tomiyama@mech.kobe-u.ac.jp
Kobe University,
1-1 Rokkodai, Nada-ku,
Kobe-shi 657-8501, Hyogo, Japan
e-mail: tomiyama@mech.kobe-u.ac.jp
1Corresponding author.
Manuscript received May 25, 2017; final manuscript received February 15, 2018; published online May 16, 2018. Assoc. Editor: Walter Ambrosini.
ASME J of Nuclear Rad Sci. Jul 2018, 4(3): 031001 (8 pages)
Published Online: May 16, 2018
Article history
Received:
May 25, 2017
Revised:
February 15, 2018
Citation
Murase, M., Kusunoki, T., Nishida, K., Goda, R., and Tomiyama, A. (May 16, 2018). "Correlation of Interfacial Friction Coefficients for Predicting Countercurrent Flow Limitation at a Sharp-Edged Lower End of Vertical Pipes." ASME. ASME J of Nuclear Rad Sci. July 2018; 4(3): 031001. https://doi.org/10.1115/1.4039438
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