Two-Phase Void Fraction and Pressure Drop in Horizontal Crossflow Across a Tube Bundle

1998 ◽  
Vol 120 (1) ◽  
pp. 140-145 ◽  
Author(s):  
G. P. Xu ◽  
K. W. Tou ◽  
C. P. Tso
Keyword(s):  
Pressure Drop ◽  
Void Fraction ◽  
Mass Velocity ◽  
Flow Model ◽  
Tube Bundle ◽  
Diameter Ratio ◽  
Two Phase ◽  
Friction Pressure ◽  
Oil Flow ◽  
Friction Pressure Drop

Void fraction and friction pressure drop measurements were made for an adiabatic, horizontal two-phase flow of air-water, air-oil across a horizontal in-line, 5 × 20 tube bundle with pitch-to-diameter ratio, P/D, of 1.28. For both air-water and air-oil flow, the experimental results showed that the average void fraction were less than the values predicted by a homogenous flow model, but were well correlated with the Martinelli parameter Xtt and liquid-only Froude number FrLO. The two-phase friction multiplier data exhibited an effect of flow pattern and mass velocity, and they could be well-correlated with the Martinelli parameter.

Hydrodynamics of Two-Phase Flow Across Horizontal In-line and Staggered Rod Bundles

1992 ◽  
Vol 114 (3) ◽  
pp. 450-456 ◽  
Author(s):  
R. Dowlati ◽  
A. M. C. Chan ◽  
M. Kawaji
Keyword(s):  
Pressure Drop ◽  
Void Fraction ◽  
Flow Model ◽  
Two Phase Flow ◽  
Phase Flow ◽  
Gas Velocity ◽  
Rod Bundles ◽  
Two Phase ◽  
Friction Pressure Drop ◽  
Velocity Effect

The void fraction and friction pressure drop measurements have been made for vertical two-phase flow of air-water across staggered and in-line rod bundles with different pitch-to-diameter ratios. All void fraction data showed a strong mass velocity effect and were significantly less than the values predicted by a homogeneous flow model, but were well correlated using the dimensionless gas velocity, jg*. The two-phase friction multiplier data could be well correlated with the Martinelli parameter for G > 200 kg/m2s. The correlations developed for void fraction and two-phase friction multiplier were successfully tested in predicting the total pressure drop in boiling R-113 experiments.

Paper 7: Mass Flow Prediction in Natural Circulation Boilers

1969 ◽  
Vol 184 (7) ◽  
pp. 6-15
Author(s):  
A. S. T. Thomson ◽  
A. W. Scott ◽  
D. H. Rooney ◽  
A. M. Bradford
Keyword(s):  
Void Fraction ◽  
Flow Model ◽  
Natural Circulation ◽  
Circulation Rate ◽  
Two Phase ◽  
Flow Prediction ◽  
Friction Pressure ◽  
Type Flow ◽  
Friction Pressure Drop ◽  
Theoretical Results

This paper presents results from a programme of steady-state natural circulation tests carried out on a two-tube experimental boiler. The circuit was constructed using normal commercial tubes and the tests covered the following range of variables: During the tests, measurements were taken of pressure, pressure difference, circulation rate, and density or void fraction at the top of the riser tube. The void fraction data are presented for use. A theoretical analysis was carried out using an annular type flow model in the riser tube with a simple two-phase friction pressure drop expression which required only void fraction data. A comparison was made between the theoretical results and the experimental data and the comparison was extended to include ( a) homogeneous flow, ( b) Martinelli–Nelson correlation, and ( c) Thom correlation. The results indicate that the analysis used, which requires only void fraction data, gave the best correlation over the range of natural circulation conditions covered.

scholarly journals Simulation of the two-phase flow across tube bundle

2021 ◽  
Vol 2088 (1) ◽  
pp. 012031
Author(s):  
Hossein Abdi ◽  
O I Melikhov ◽  
V I Melikhov
Keyword(s):  
Mass Velocity ◽  
Two Phase Flow ◽  
Tube Bundle ◽  
Diameter Ratio ◽  
Phase Flow ◽  
Rod Bundles ◽  
Two Phase ◽  
Horizontal Steam Generator ◽  
Gamma Densitometer ◽  
Hydraulic Processes

Abstract Experiments on two-phase flow across an in-line tube bundle are analyzed with the STEG code, which has been developed for modeling thermal-hydraulic processes in a horizontal steam generator (SG). An adiabatic, vertical two-phase flows of air-water across horizontal in-line, 5 x 20 rod bundles, with a pitch-to-diameter ratio P/D=1.3 are considered, the mass velocity is varied in the range 27 - 818 kg/m2s. The calculated values of void fraction in the tube bundle are compared with the experimental ones measured by a gamma densitometer. A reasonable agreement between the calculations and the experimental data is obtained.

scholarly journals Friction pressure drop model of gas-liquid two-phase flow in an inclined pipe with high gas and liquid velocities

AIP Advances ◽  
2019 ◽  
Vol 9 (8) ◽  
pp. 085025
Author(s):  
Zilong Liu ◽  
Ruiquan Liao ◽  
Wei Luo ◽  
Joseph X. F. Ribeiro ◽  
Yubin Su
Keyword(s):  
Pressure Drop ◽  
Two Phase Flow ◽  
Phase Flow ◽  
Two Phase ◽  
Friction Pressure ◽  
Friction Pressure Drop ◽  
Inclined Pipe

Two-Phase Crossflow and Boiling Heat Transfer in Horizontal Tube Bundles

1996 ◽  
Vol 118 (1) ◽  
pp. 124-131 ◽  
Author(s):  
R. Dowlati ◽  
M. Kawaji ◽  
A. M. C. Chan
Keyword(s):  
Heat Transfer ◽  
Heat Transfer Coefficient ◽  
Pressure Drop ◽  
Transfer Coefficient ◽  
Void Fraction ◽  
Mass Velocity ◽  
Flow Boiling ◽  
Horizontal Tube ◽  
Two Phase ◽  
Tube Bundles

An experimental study has been conducted to determine the void fraction, frictional pressure drop, and heat transfer coefficient for vertical two-phase crossflow of refrigerant R-113 in horizontal tube bundles under saturated flow boiling conditions. The tube bundle contained 5 × 20 tubes in a square in-line array with pitch-to-diameter ratio of 1.3. R-113 mass velocity ranged from 50 to 970 kg/m2s and test pressure from 103 to 155 kPa. The void fraction data exhibited strong mass velocity effects and were significantly less than the homogeneous and in-tube flow model predictions. They were found to be well correlated in terms of the dimensionless gas velocity, jg*. The two-phase friction multiplier data could be correlated well in terms of the Lockhart–Martinelli parameter. The validity of these correlations was successfully tested by predicting the total pressure drop from independent R-113 boiling experiments. The two-phase heat transfer coefficient data were found to agree well with existing pool boiling correlations, implying that nucleate boiling was the dominant heat transfer mode in the heat flux range tested.

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