Characterization of horizontal air-water two-phase flow

R. Kong, S. Kim

    Research output: Chapter in Book/Report/Conference proceedingConference contribution

    2 Citations (Scopus)

    Abstract

    This paper presents experimental studies performed to characterize horizontal air-water two-phase flow in a round pipe with an inner diameter of 38.1mm. A detailed flow visualization study is performed using a high-speed movie camera in a wide range of two-phase flow conditions. Two-phase flows are classified into bubbly, plug, slug, stratified, stratified-wavy, and annular flow regimes. While the transition boundaries identified in the present study compare well with the existing ones in general, some discrepancies are observed for the boundaries of bubbly-to-plug, bubbly-to-slug, and plug-to-slug flows. Two-phase frictional pressure loss analysis is performed using the Lockhart-Martinelli method. For the conditions studied in the present study, it is found that the coefficient C= 24 yields the best agreement with the data with the minimum average disagreement. Detailed local experiments are performed in a wide range of conditions in the bubbly flow regime using a four-sensor conductivity probe. An extensive database for local two-phase flow parameters is established, including void fraction, bubble velocity, interfacial area concentration and bubble Sauter mean diameter. Based on this database, functional relations for ((vg)) vs. (/'> and {a) vs. (jg)/(j) have been studied. It is found that ((vg))-(j) method predicts the bubble velocity and void fraction better compared to (a)-(jg)/(j) method. Additionally, the evolution of various local two-phase flow parameters in horizontal bubbly two-phase flow is studied by analyzing the measured local parameters along the flow field. Unlike vertical upward bubbly flow, the local void fraction and interfacial area concentration can reach 0.6 and 2000 1/m, respectively, in horizontal bubbly flow. It's noticed that bubbles begin to coalesce near the gas-liquid layer instead of in the highly packed region when gas volumetric flux increases.

    Original languageEnglish (US)
    Title of host publicationInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
    PublisherAmerican Nuclear Society
    Pages5559-5572
    Number of pages14
    Volume7
    ISBN (Electronic)9781510811843
    StatePublished - 2015
    Event16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States
    Duration: Aug 30 2015Sep 4 2015

    Other

    Other16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
    CountryUnited States
    CityChicago
    Period8/30/159/4/15

    Fingerprint

    two phase flow
    Two phase flow
    Void fraction
    air
    bubbles
    plugs
    Air
    Bubbles (in fluids)
    water
    Water
    voids
    annular flow
    stratified flow
    high speed cameras
    High speed cameras
    flow visualization
    Flow visualization
    Gases
    gases
    Flow fields

    All Science Journal Classification (ASJC) codes

    • Instrumentation
    • Nuclear Energy and Engineering

    Cite this

    Kong, R., & Kim, S. (2015). Characterization of horizontal air-water two-phase flow. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015 (Vol. 7, pp. 5559-5572). American Nuclear Society.
    Kong, R. ; Kim, S. / Characterization of horizontal air-water two-phase flow. International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. Vol. 7 American Nuclear Society, 2015. pp. 5559-5572
    @inproceedings{789be2f6b8a542faa517f5f09e02c780,
    title = "Characterization of horizontal air-water two-phase flow",
    abstract = "This paper presents experimental studies performed to characterize horizontal air-water two-phase flow in a round pipe with an inner diameter of 38.1mm. A detailed flow visualization study is performed using a high-speed movie camera in a wide range of two-phase flow conditions. Two-phase flows are classified into bubbly, plug, slug, stratified, stratified-wavy, and annular flow regimes. While the transition boundaries identified in the present study compare well with the existing ones in general, some discrepancies are observed for the boundaries of bubbly-to-plug, bubbly-to-slug, and plug-to-slug flows. Two-phase frictional pressure loss analysis is performed using the Lockhart-Martinelli method. For the conditions studied in the present study, it is found that the coefficient C= 24 yields the best agreement with the data with the minimum average disagreement. Detailed local experiments are performed in a wide range of conditions in the bubbly flow regime using a four-sensor conductivity probe. An extensive database for local two-phase flow parameters is established, including void fraction, bubble velocity, interfacial area concentration and bubble Sauter mean diameter. Based on this database, functional relations for ((vg)) vs. (/'> and {a) vs. (jg)/(j) have been studied. It is found that ((vg))-(j) method predicts the bubble velocity and void fraction better compared to (a)-(jg)/(j) method. Additionally, the evolution of various local two-phase flow parameters in horizontal bubbly two-phase flow is studied by analyzing the measured local parameters along the flow field. Unlike vertical upward bubbly flow, the local void fraction and interfacial area concentration can reach 0.6 and 2000 1/m, respectively, in horizontal bubbly flow. It's noticed that bubbles begin to coalesce near the gas-liquid layer instead of in the highly packed region when gas volumetric flux increases.",
    author = "R. Kong and S. Kim",
    year = "2015",
    language = "English (US)",
    volume = "7",
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    booktitle = "International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015",
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    Kong, R & Kim, S 2015, Characterization of horizontal air-water two-phase flow. in International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. vol. 7, American Nuclear Society, pp. 5559-5572, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015, Chicago, United States, 8/30/15.

    Characterization of horizontal air-water two-phase flow. / Kong, R.; Kim, S.

    International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. Vol. 7 American Nuclear Society, 2015. p. 5559-5572.

    Research output: Chapter in Book/Report/Conference proceedingConference contribution

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    AU - Kim, S.

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    N2 - This paper presents experimental studies performed to characterize horizontal air-water two-phase flow in a round pipe with an inner diameter of 38.1mm. A detailed flow visualization study is performed using a high-speed movie camera in a wide range of two-phase flow conditions. Two-phase flows are classified into bubbly, plug, slug, stratified, stratified-wavy, and annular flow regimes. While the transition boundaries identified in the present study compare well with the existing ones in general, some discrepancies are observed for the boundaries of bubbly-to-plug, bubbly-to-slug, and plug-to-slug flows. Two-phase frictional pressure loss analysis is performed using the Lockhart-Martinelli method. For the conditions studied in the present study, it is found that the coefficient C= 24 yields the best agreement with the data with the minimum average disagreement. Detailed local experiments are performed in a wide range of conditions in the bubbly flow regime using a four-sensor conductivity probe. An extensive database for local two-phase flow parameters is established, including void fraction, bubble velocity, interfacial area concentration and bubble Sauter mean diameter. Based on this database, functional relations for ((vg)) vs. (/'> and {a) vs. (jg)/(j) have been studied. It is found that ((vg))-(j) method predicts the bubble velocity and void fraction better compared to (a)-(jg)/(j) method. Additionally, the evolution of various local two-phase flow parameters in horizontal bubbly two-phase flow is studied by analyzing the measured local parameters along the flow field. Unlike vertical upward bubbly flow, the local void fraction and interfacial area concentration can reach 0.6 and 2000 1/m, respectively, in horizontal bubbly flow. It's noticed that bubbles begin to coalesce near the gas-liquid layer instead of in the highly packed region when gas volumetric flux increases.

    AB - This paper presents experimental studies performed to characterize horizontal air-water two-phase flow in a round pipe with an inner diameter of 38.1mm. A detailed flow visualization study is performed using a high-speed movie camera in a wide range of two-phase flow conditions. Two-phase flows are classified into bubbly, plug, slug, stratified, stratified-wavy, and annular flow regimes. While the transition boundaries identified in the present study compare well with the existing ones in general, some discrepancies are observed for the boundaries of bubbly-to-plug, bubbly-to-slug, and plug-to-slug flows. Two-phase frictional pressure loss analysis is performed using the Lockhart-Martinelli method. For the conditions studied in the present study, it is found that the coefficient C= 24 yields the best agreement with the data with the minimum average disagreement. Detailed local experiments are performed in a wide range of conditions in the bubbly flow regime using a four-sensor conductivity probe. An extensive database for local two-phase flow parameters is established, including void fraction, bubble velocity, interfacial area concentration and bubble Sauter mean diameter. Based on this database, functional relations for ((vg)) vs. (/'> and {a) vs. (jg)/(j) have been studied. It is found that ((vg))-(j) method predicts the bubble velocity and void fraction better compared to (a)-(jg)/(j) method. Additionally, the evolution of various local two-phase flow parameters in horizontal bubbly two-phase flow is studied by analyzing the measured local parameters along the flow field. Unlike vertical upward bubbly flow, the local void fraction and interfacial area concentration can reach 0.6 and 2000 1/m, respectively, in horizontal bubbly flow. It's noticed that bubbles begin to coalesce near the gas-liquid layer instead of in the highly packed region when gas volumetric flux increases.

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    M3 - Conference contribution

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    Kong R, Kim S. Characterization of horizontal air-water two-phase flow. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. Vol. 7. American Nuclear Society. 2015. p. 5559-5572