This paper presents an experimental study of local liquid velocity measurement in downward air-water bubbly and slug flows in a 50.8 mm inner-diameter round pipe. The axial liquid velocity and its fluctuations were measured by a laser Doppler anemometry (LDA) system. It was found that the maximum liquid velocity in a downward two-phase flow could occur off the pipe centerline at relatively low liquid flow rates and this observation is consistent with other researchers’ results. The comparisons between the liquid flow rates measured by a magnetic flow meter and those obtained from the local LDA and multi-sensor conductivity probe measurements showed good agreement. In addition, based on the local measurements the distribution parameter and the drift velocity in the drift-flux model were obtained for the current downward flow tests.
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July 2004
Technical Papers
Local Liquid Velocity in Vertical Air-Water Downward Flow
Xiaodong Sun,
Xiaodong Sun
Thermal-Hydraulics and Reactor Safety Laboratory, School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907, USA
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Sidharth Paranjape,
Sidharth Paranjape
Thermal-Hydraulics and Reactor Safety Laboratory, School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907, USA
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Seungjin Kim,
Seungjin Kim
Thermal-Hydraulics and Reactor Safety Laboratory, School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907, USA
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Hiroshi Goda,
Hiroshi Goda
Thermal-Hydraulics and Reactor Safety Laboratory, School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907, USA
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Mamoru Ishii,
Mamoru Ishii
Thermal-Hydraulics and Reactor Safety Laboratory, School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907, USA
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Joseph M. Kelly
Joseph M. Kelly
U.S. Nuclear Regulatory Commission, Mail Stop: T10K8, 11545 Rockville Pike, Rockville, MD 20852, USA
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Xiaodong Sun
Thermal-Hydraulics and Reactor Safety Laboratory, School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907, USA
Sidharth Paranjape
Thermal-Hydraulics and Reactor Safety Laboratory, School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907, USA
Seungjin Kim
Thermal-Hydraulics and Reactor Safety Laboratory, School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907, USA
Hiroshi Goda
Thermal-Hydraulics and Reactor Safety Laboratory, School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907, USA
Mamoru Ishii
Thermal-Hydraulics and Reactor Safety Laboratory, School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907, USA
Joseph M. Kelly
U.S. Nuclear Regulatory Commission, Mail Stop: T10K8, 11545 Rockville Pike, Rockville, MD 20852, USA
Contributed by the Fluids Engineering Division for publication in the JOURNAL OF FLUIDS ENGINEERING. Manuscript received by the Fluids Engineering Division May 27, 2003; revised manuscript received July 15, 2003. Associate Editor: J. Katz.
J. Fluids Eng. Jul 2004, 126(4): 539-545 (7 pages)
Published Online: September 10, 2004
Article history
Received:
May 27, 2003
Revised:
July 15, 2003
Online:
September 10, 2004
Citation
Sun, X., Paranjape , S., Kim, S., Goda, H., Ishii, M., and Kelly, J. M. (September 10, 2004). "Local Liquid Velocity in Vertical Air-Water Downward Flow ." ASME. J. Fluids Eng. July 2004; 126(4): 539–545. https://doi.org/10.1115/1.1777235
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