An improved void fraction model for two-phase cross-flow in horizontal tube bundles

2000 ◽  
Vol 26 (11) ◽  
pp. 1851-1873 ◽  
Author(s):  
P.A. Feenstra ◽  
D.S. Weaver ◽  
R.L. Judd
Entropy ◽  
2021 ◽  
Vol 23 (10) ◽  
pp. 1355
Author(s):  
Claire Dubot ◽  
Cyrille Allery ◽  
Vincent Melot ◽  
Claudine Béghein ◽  
Mourad Oulghelou ◽  
...  

Predicting the void fraction of a two-phase flow outside of tubes is essential to evaluate the thermohydraulic behaviour in steam generators. Indeed, it determines two-phase mixture properties and affects two-phase mixture velocity, which enable evaluating the pressure drop of the system. The two-fluid model for the numerical simulation of two-phase flows requires interaction laws between phases which are not known and/or reliable for a flow within a tube bundle. Therefore, the mixture model, for which it is easier to implement suitable correlations for tube bundles, is used. Indeed, by expressing the relative velocity as a function of slip, the void fraction model of Feenstra et al.and Hibiki et al. developed for upward cross-flow through horizontal tube bundles is introduced and compared. With the method suggested in this paper, the physical phenomena that occur in tube bundles are taken into consideration. Moreover, the tube bundle is modelled using a porous media approach where the Darcy–Forchheimer term is usually defined by correlations found in the literature. However, for some tube bundle geometries, these correlations are not available. The second goal of the paper is to quickly compute, in quasi-real-time, this term by a non-intrusive parametric reduced model based on Proper Orthogonal Decomposition. This method, named Bi-CITSGM (Bi-Calibrated Interpolation on the Tangent Subspace of the Grassmann Manifold), consists in interpolating the spatial and temporal bases by ITSGM (Interpolation on the Tangent Subspace of the Grassmann Manifold) in order to define the solution for a new parameter. The two developed methods are validated based on the experimental results obtained by Dowlati et al. for a two-phase cross-flow through a horizontal tube bundle.


2005 ◽  
Vol 4 (2) ◽  
Author(s):  
G. Ribatskia ◽  
J. R. Thome

This paper presents a state-of-the-art review of the hydrodynamic aspects of two-phase flow across horizontal tube bundles. The review covers studies related to the evaluation of void fraction, two-phase flow behaviors and pressure drops on the shell side of staggered and in-line tube bundles for upward, downward and side-to-side flows. This study of the literature critically describes the proposed flow pattern maps and semi-empirical correlations for predicting void fraction and frictional pressure drop. These predicting methods are generally based on experimental results for adiabatic air-water flows. A limited number of experimental studies with R-11 and R-113 were also carried out in the past. The review shows noticeable discrepancies among the available prediction methods. Finally, this study suggests that further research focusing on the development of representative databanks and new prediction methods is still necessary.


Author(s):  
W. G. Sim

An approximate analytical model, to predict the two-phase damping for upward cross-flow through horizontal bundles, has been developed. This model will allow researches to provide analytical estimates of the damping ratios. The existing semiempirical approach by Pettigrew and Taylor (2003) was approximated by taking the lower envelope of the damping data. To estimate the void fraction for the cross-flow, the void fraction model proposed by Feenstra etc (2000) is utilized. The development of the present damping model stemmed from the two-phase multiplier of pressure loss and the momentum flux of the two-phase flow. The important variables on the damping are identified. The results of the present model agree well with experimental damping ratios in air-mixtures for a sufficiently wide range of pitch mass ratio, quality and p/d ratios. It has also shown predictive capability for steam-water mixtures and Freon 11.


2006 ◽  
Vol 27 (3) ◽  
pp. 5-21 ◽  
Author(s):  
Lorenzo Consolini ◽  
Douglas Robinson ◽  
John R. Thome

1989 ◽  
Vol 111 (4) ◽  
pp. 488-500 ◽  
Author(s):  
C. E. Taylor ◽  
I. G. Currie ◽  
M. J. Pettigrew ◽  
B. S. Kim

An extensive experimental program was carried out to study the vibration behavior of tube bundles subjected to two-phase cross-flow. Turbulence-induced excitation is discussed in Part 3 of this series of three papers. Random vibration response to turbulence-induced excitation is a significant vibration mechanism in heat exchanger tube bundles subjected to two-phase cross-flow. The vibration responses of centrally located tubes in four tube bundle configurations subjected to air-water cross-flow was measured. The results are presented in the form of a normalized forced-excitation spectrum which can be used as a design guideline over a void fraction range from 25 percent to 99 percent and over a practical range of flow rates. The data are further analyzed to determine the dependence of the vibration response on Reynolds number, void fraction and frequency. Measurements taken on a single tube, a row of tubes and on tubes having varying end conditions were used to assist in interpreting the bundle data.


1996 ◽  
Vol 118 (1) ◽  
pp. 124-131 ◽  
Author(s):  
R. Dowlati ◽  
M. Kawaji ◽  
A. M. C. Chan

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.


Author(s):  
Fabio Toshio Kanizawa ◽  
Leopoldo P. R. de Oliveira ◽  
Gherhardt Ribatski

This paper presents a comprehensive review on the open literature concerning two-phase flow across horizontal tube bundles. Initially, experimental studies available in the literature are described in an organized manner. This detailed description includes bundle configurations and the experimental techniques used for evaluating flow patterns, void fraction and flow-induced vibration. Most of studies were performed having air-water as working fluids. Several excitation mechanisms can be reproduced such as flow periodicity, fluid-elasticity and turbulence. Flow patterns are discussed and their predictive methods are compared. Void fraction predictive methods are also discussed and comparisons among them are presented. It was found that the predictive methods worked reasonably well when compared against the databases used during their development. Generally, the studies have obtained bundle average measurements which are not representative of the local conditions and, therefore, are not recommendable to be used as accurate designing tools. Most studies concerning fluid-induced vibration have addressed this problem through simplified bench structures, usually consisting of a single rigid tube over a flexible suspension.


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