In the case of loss of the residual heat removal system under mid-loop operation during shutdown of the pressurized water reactor (PWR) plant, steam generated in a reactor core and condensed water in a steam generator (SG) form a countercurrent flow in a hot leg. In this study, in order to improve a counter-current flow model of a transient analysis code, experiments were conducted using a scale-down model of the PWR hot leg, and flow patterns and counter-current flow limitation (CCFL) characteristics were measured. A rectangular duct, whose height is about 1/5th of the hot leg diameter, was used to simulate the hot leg, and air and water at atmospheric pressure and room temperature were used for gas and liquid phases. In the horizontal section, as air flow rate QG increases, the flow pattern transits from a stratified flow to wavy flow, and then wavy to wavy-mist flow. When the latter transition takes place, water flow from the horizontal duct to the lower tank is to be restricted. Flow patterns in the elbow section are the same as those in the horizontal section. Wavy flow is not formed in the inclined section, where the transition to wavy-mist flow occurs due to the inflow of wavy-mist flow generated in the horizontal section. Flow patterns in the elbow and inclined section are strongly affected by those in the horizontal section. CCFL characteristics are well correlated with the Wallis-type correlation, and the onset of CCFL well corresponds to the transition from wavy flow to wavy-mist flow.
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16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4816-7
PROCEEDINGS PAPER
Experiments on Air-Water Countercurrent Flow in a Rectangular Duct Simulating PWR Hot Leg
Noritoshi Minami,
Noritoshi Minami
Institute of Nuclear Safety System, Inc., Fukui, Japan
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Daisuke Nishiwaki,
Daisuke Nishiwaki
Kobe University, Kobe, Hyogo, Japan
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Hironobu Kataoka,
Hironobu Kataoka
Kobe University, Kobe, Hyogo, Japan
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Akio Tomiyama,
Akio Tomiyama
Kobe University, Kobe, Hyogo, Japan
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Shigeo Hosokawa,
Shigeo Hosokawa
Kobe University, Kobe, Hyogo, Japan
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Michio Murase
Michio Murase
Institute of Nuclear Safety System, Inc., Fukui, Japan
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Noritoshi Minami
Institute of Nuclear Safety System, Inc., Fukui, Japan
Daisuke Nishiwaki
Kobe University, Kobe, Hyogo, Japan
Hironobu Kataoka
Kobe University, Kobe, Hyogo, Japan
Akio Tomiyama
Kobe University, Kobe, Hyogo, Japan
Shigeo Hosokawa
Kobe University, Kobe, Hyogo, Japan
Michio Murase
Institute of Nuclear Safety System, Inc., Fukui, Japan
Paper No:
ICONE16-48113, pp. 127-134; 8 pages
Published Online:
June 24, 2009
Citation
Minami, N, Nishiwaki, D, Kataoka, H, Tomiyama, A, Hosokawa, S, & Murase, M. "Experiments on Air-Water Countercurrent Flow in a Rectangular Duct Simulating PWR Hot Leg." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 3: Thermal Hydraulics; Instrumentation and Controls. Orlando, Florida, USA. May 11–15, 2008. pp. 127-134. ASME. https://doi.org/10.1115/ICONE16-48113
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