Interfacial friction factors in vertical circular pipes under flooding conditions at the bottom end
- 1. Institute of Nuclear Safety System, Inc., Mihama, Fukui (Japan)
- 2. Kobe University, Graduate School of Engineering, Kobe, Hyogo (Japan)
Description
In our previous study (Goda et al.), we measured the void fraction α, pressure gradient dP/dz, and countercurrent flow limitation (i.e. relationship between superficial velocities, JG and JL) in vertical pipes (diameter D = 20 and 40 mm) under flooding conditions at the square bottom end and working fluids of air and water to obtain the wall friction factor fw and the interfacial friction factor fi based on the annular flow model. Measurements of α in vertical pipes under flooding conditions are few. In this study, therefore, we evaluated fi from the measured dP/dz under flooding at the square bottom end reported by Bharathan et al. with D = 6.4 to 152 mm and air-water and by Ilyukhin et al. with D = 20 mm and working fluids of steam and water at pressures of P = 0.6 to 4.1 MPa. As a result, we found that the fi values obtained from the measured dP/dz and the fw correlation by Goda et al. were well correlated in terms of the gas Kutateladze parameter KG* and the dimensionless diameter D*. The effect of fluid properties was expressed by a revision term with the viscosity ratio of gas and liquid phases (μG/μL). (author)
Availability note (English)
Available from https://doi.org/10.3811/jjmf.2020.007Additional details
Additional titles
- Original title (Japanese)
- 下端フラッディング状態での鉛直円管内における界面摩擦係数
Identifiers
Publishing Information
- Journal Title
- Konsoryu (Online)
- Journal Volume
- 34
- Journal Issue
- 1
- Series
- 雑誌名:混相流
- Journal Page Range
- p. 82-92
- ISSN
- 1881-5790
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51090930
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- CORRELATIONS; COUNTER CURRENT; FLOW RATE; FLUID MECHANICS; FRICTION FACTOR; LAMINAR FLOW; LOSS OF COOLANT; PRESSURE GRADIENTS; PWR TYPE REACTORS; STEAM GENERATORS; TURBULENT FLOW; TWO-PHASE FLOW; VISCOSITY; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; BOILERS; DIMENSIONLESS NUMBERS; ENRICHED URANIUM REACTORS; FLUID FLOW; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 20 refs., 14 figs., 1 tab.