Interfacial area transport in horizontal bubbly flow with 90-degree elbow

Seungjin Kim, Kennard Callender, Gunol Kojasoy

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

    Abstract

    The present study develops an interfacial area transport equation applicable to an air-water horizontal bubbly flow with a flow restriction. The experiments are performed in a round glass pipe of 50.3 mm inner diameter, along which a 90-degee elbow is installed at L/D=206.6 from the two-phase mixture inlet. In total, 15 different flow conditions in the bubbly flow regime are studied. The detailed local two-phase flow parameters are acquired by a double-sensor conductivity probe at four different axial locations. The effect of elbow is evident in the distribution of local parameters as well as in the development of interfacial structures. The elbow clearly promotes bubble interactions resulting in significant changes in both the void fraction and interfacial area concentration. In the present study, the elbow is found to promote the coalescence mechanism, while reducing the disintegration mechanism. These geometric effects are also reflected in the axial development of one-dimensional two-phase flow parameters. In the present analysis, the interfacial area transport equation is developed in one-dimensional form via area averaging based on the existing model for vertical flow. In the averaging process, characteristic non-uniform distributions of the two-phase flow parameters in horizontal two-phase flow are treated mathematically by covariance calculations. Furthermore, the change in pressure due to the minor loss of the elbow is taken into consideration by using a newly developed correlation analogous to Lockhart and Martinelli's. In total, 60 area-averaged data points are employed to benchmark the present model. The present model predicts the data well with an average percent difference of approximately ±10%.

    Original languageEnglish (US)
    Title of host publicationProceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12
    StatePublished - Dec 1 2007
    Event12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12 - Pittsburgh, PA, United States
    Duration: Sep 30 2007Oct 4 2007

    Publication series

    NameProceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12

    Other

    Other12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12
    CountryUnited States
    CityPittsburgh, PA
    Period9/30/0710/4/07

    All Science Journal Classification (ASJC) codes

    • Nuclear Energy and Engineering
    • Nuclear and High Energy Physics

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