A study of the performance of void fraction correlations used in the context of drift-flux two-phase flow models

Coddington, Paul; Macian, Rafael

doi:10.1016/s0029-5493(01)00503-9

Cited by 169 publications

(82 citation statements)

References 12 publications

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“…4, have been found to be 0.0036, 0.029 and 0.029, respectively. The former two parameters are seen to compare quite favourably with the corresponding values of 0.019 and 0.103, respectively, reported in Coddington and Macian 10) for the void fraction range of 0.0 to 1.0. (The larger standard deviation in the latter case (see Fig.…”

Section: Confirmatory Results For Watersupporting

confidence: 69%

“…From the results presented in Table 2 for the loop data, very small values of both the standard deviation and the root-mean-square error are observed for all three formalisms of the relative drift velocity. These values are smaller than the corresponding ones for water, 10) although it needs to be noted that, for the heavy liquid metal analysis, the void fractions have an upper bound of $0:4. In all three cases, the phase distribution parameter C 0 is observed to be less than 1.0.…”

Section: Heavy Liquid Metal Data Analysismentioning

confidence: 65%

“…Accordingly, before starting the liquid metal data analysis, a qualification of the test data was performed by comparing the water test results with existing drift-flux correlations. For the purpose, the Toshiba correlation, one of the simplest in the review made by Coddington and Macian, 10) was chosen, with C 0 ¼1:08 and v gj ¼0:45 m/s, viz. : Figure 4 shows that the predictions made with this correlation are in good agreement with the water data for both pool-and loop-tests.…”

Section: Confirmatory Results For Watermentioning

confidence: 99%

“…10) In particular, in order to estimate the quality of the predictions made, the absolute error for each data point was evaluated as…”

Section: Analytical Study 1 Basic Approachmentioning

confidence: 99%

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Development of a Drift-flux Model for Heavy Liquid Metal/Gas Flow

Mikityuk

Coddington

Chawla

2005

Journal of Nuclear Science and Technology

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The gas lift pump concept based on the bubbling of an inert gas into the primary reactor coolant to enhance natural circulation is currently considered in a number of PbBi-cooled reactor concepts. Thus, the analysis of available void fraction data and the development of two-phase heavy liquid metal/gas flow calculational models have become an important issue in the study of advanced nuclear reactor systems. In the absence of the detailed two-phase flow information needed to develop a flow regime map and the associated interfacial relations, drift-flux models have often been used in the thermal-hydraulic analysis of nuclear and other systems. Accordingly, we consider, in the current paper, the analysis of five sets of experimental data with different geometries, working fluids, flow rates and void fraction ranges, with a view to obtaining a best fit to the data in the form of a drift-flux model. The results of the analysis show that, for systems with flowing fluid, it is possible to represent the heavy liquid metal void fraction data in the form of a drift-flux correlation with a residual error of as low as 0.016, thus offering an improvement over existing void correlations.

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Section: Confirmatory Results For Watersupporting

confidence: 69%

Section: Heavy Liquid Metal Data Analysismentioning

confidence: 65%

Section: Confirmatory Results For Watermentioning

confidence: 99%

“…10) In particular, in order to estimate the quality of the predictions made, the absolute error for each data point was evaluated as…”

Section: Analytical Study 1 Basic Approachmentioning

confidence: 99%

See 2 more Smart Citations

Development of a Drift-flux Model for Heavy Liquid Metal/Gas Flow

Mikityuk

Coddington

Chawla

2005

Journal of Nuclear Science and Technology

Self Cite

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“…The first 4 sets such as the constitutive equations of Bestion,11) Chexal et al, 12) Inoue et al, 13) and Maier and Coddington 14) have been derived from rod bundle data (mainly differential pressure measurements) and have been successfully tested against different rod bundle databases 16) in a wide range of void fraction conditions. The last set such as the constitutive equations of Hibiki et al 15) was derived for annulus channel geometry and obtained by local probe measurements.…”

Section: Survey Of Existing Work 1 One-dimensional Drift-flux Mmentioning

confidence: 99%

Flow Structure of Subcooled Boiling Water Flow in a Subchannel of 3×3 Rod Bundles

Yun

Park

Juliá

et al. 2008

J. Nucl. Sci. Technol.

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In this paper, the interfacial flow structure of subcooled water boiling flow in a subchannel of 3 Â 3 rod bundles is presented. The 9 rods are positioned in a quadrangular assembly with a rod diameter of 8.2 mm and a pitch distance of 16.6 mm. Local void fraction, interfacial area concentration, interfacial velocity, Sauter mean diameter, and liquid velocity have been measured using a conductivity probe and a Pitot tube in 20 locations inside one of the subchannels. A total of 53 flow conditions have been considered in the experimental dataset at atmospheric pressure conditions with a mass flow rate, heat flux, inlet temperature, and subcooled temperature ranges of 250-522 kg/m 2 s, 25-185 kW/m 2 , 96.6-104.9 C, and 2-11 K, respectively. The dataset has been used to analyze the effect of the heat flux and mass flow rate on the local flow parameters. In addition, the area-averaged data integrated over the whole subchannel have been used to validate some of the distribution parameter and drift velocity constitutive equations and interfacial area concentration correlations most used in the literature.

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Improved Void Fraction Correlation for Two‐Phase Flow in Large‐Diameter Annuli

et al. 2017

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A flow pattern-independent void fraction correlation for gas-liquid two-phase flow in vertical large-diameter annuli is established. Two equations are proposed for the parameters of a drift flux model-based correlation: the distribution parameter and the drift flux velocity. These equations are expressed as a function of two-phase flow variables including void fraction, fluid properties, pipe geometry, and phase flow rates. Experiments were performed to study the void fraction of vertical air-water two-phase flow in large-diameter annuli. The obtained experimental data along with the literature data of Caetano are used to verify the performance of the proposed void fraction correlation. The accuracy of this correlation is compared with nineteen frequently used correlations in literature. The proposed correlation was found to predict the void fraction consistently with a better accuracy.

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A study of the performance of void fraction correlations used in the context of drift-flux two-phase flow models

Cited by 169 publications

References 12 publications

Development of a Drift-flux Model for Heavy Liquid Metal/Gas Flow

Development of a Drift-flux Model for Heavy Liquid Metal/Gas Flow

Flow Structure of Subcooled Boiling Water Flow in a Subchannel of 3×3 Rod Bundles

Improved Void Fraction Correlation for Two‐Phase Flow in Large‐Diameter Annuli

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