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Effects of fluid properties on CCFL characteristics at a vertical pipe lower end
Authors:Takayoshi Kusunoki  Michio Murase  Yuki Fujii  Takahiro Nozue  Kosuke Hayashi  Shigeo Hosokawa
Affiliation:1. Graduate School of Engineering, Kobe University, 1-1 Rokkodai-cho, Nada-ku, Kobe 657-8501, Japan;2. Institute of Nuclear Safety System, Incorporated, 64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japankusunoki.takayoshi@inss.co.jp;4. Institute of Nuclear Safety System, Incorporated, 64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japan
Abstract:The purpose of this study is to derive a counter-current flow limitation (CCFL) correlation and evaluate its uncertainty for steam generator (SG) U-tubes in a pressurized water reactor (PWR). Experiments were conducted to evaluate effects of the liquid viscosity on CCFL characteristics using air–40 wt% or air–60 wt% glycerol water solution and saturated steam–water at atmospheric pressure with vertical pipes simulating the lower part of the SG U-tubes. The steam–water experiments confirmed that CCFL characteristics could be expressed in terms of the Wallis parameters (JG* and JL*) for the pipe diameters of D = 14, 20, and 27 mm. A CCFL correlation was derived using the ratio μGL of the viscosities of the gas and liquid phases, μG and μL, as a correction term representing effects of fluid properties, where JG*1/2GL)?0.07 was expressed by a cubic function of JL*1/2GL)0.1. In the correlation, the constant C indicating the value of JG*1/2GL)?0.07 at JL* = 0 was (1.04 ± 0.05), and this uncertainty of ±0.05 would cover most of the previous experimental data including the ROSA-IV/LSTF data at 1, 3, and 7 MPa.
Keywords:reflux condensation  steam generator  U-tube  CCFL  vertical pipe  Wallis parameter  fluid property
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