Geometric effects of 45-degree elbow in horizontal air-water bubbly flow

Justin D. Talley, Seungjin Kim, Tangwen Guo, Gunol Kojasoy

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

    3 Scopus citations

    Abstract

    The present study investigates the geometric effect of a 45-degree elbow on the development of local two-phase flow parameters and their distributions in horizontal two-phase flow. A round pipe with an inner diameter of 50.3 mm is used as a test section throughout the study. First, a 90 degree elbow is installed at L/D=206.6, then a 45-degree elbow is added at L/D=353.5 from the inlet, and local measurements are made at three different axial locations of L/D=342, 363 and 419. In total, 15 different flow conditions are investigated for the present analysis. At the measurement port just downstream of the 45-degree elbow (i.e., L/D=363), the local parameters are acquired in both the vertical and horizontal directions along the radius of pipe cross-section to capture geometric effects of the flow restriction. The local two-phase flow parameters acquired in the present study include void fraction, bubble velocity, interfacial area concentration and Sauter mean diameter. In view of one-dimensional transport, the local void fraction and interfacial area concentration are area-averaged and plotted along the axial direction. The characteristic geometric effects of the flow restrictions are clearly demonstrated in the distributions of the two-phase flow parameters and their development along the flow direction. The drastic changes in the interfacial area concentration across the elbow suggest that a 45-degree elbow induces significant changes in bubble interaction mechanisms.

    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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