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    Void Fraction Measurement and Prediction of Two-Phase Boiling Flows in a Tubular Test Section

    Source: Journal of Nuclear Engineering and Radiation Science:;2022:;volume( 009 ):;issue: 002::page 21403
    Author:
    Liu, Qingqing;Diaz, Julio;Petrov, Victor;Burak, Adam;Manera, Annalisa;Kelly, Joseph;Sun, Xiaodong
    DOI: 10.1115/1.4055002
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Void fraction is one of the most important parameters that affect two-phase flow heat transfer and pressure drop. In this paper, a commercial gamma densitometer and a high-speed X-ray radiography system developed at the University of Michigan (UM) are used to measure the void fraction in two-phase boiling flows, with water as the working fluid, in a tubular test section. The test section is made of Incoloy 800H/HT with a total length of 1.589 m, an inner diameter of 12.95 mm, and a wall thickness of 3.05 mm. These two instrumentation systems are installed on a traversing platform that travels along the vertical test section to perform measurements at multiple elevations. Subcooled flow boiling and natural convection boiling experiments are performed to measure the void fraction in the test section. Flow visualization images are obtained for bubbly and slug flows from the X-ray radiography system. The wall temperature of the test section is measured at 17 elevations by thermocouples. In addition to the experiments, a multiphase computational fluid dynamics (MCFD) model is developed using ansysfluent to simulate the subcooled flow boiling. The measured wall temperature and void fraction from the experiments are compared with the MCFD simulation results. The root-mean-square (RMS) relative deviations are 3.6% and 16.1% for the wall temperature and void fraction, respectively, between the experimental data and MCFD simulations.
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      Void Fraction Measurement and Prediction of Two-Phase Boiling Flows in a Tubular Test Section

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4288381
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    contributor authorLiu, Qingqing;Diaz, Julio;Petrov, Victor;Burak, Adam;Manera, Annalisa;Kelly, Joseph;Sun, Xiaodong
    date accessioned2022-12-27T23:19:30Z
    date available2022-12-27T23:19:30Z
    date copyright9/2/2022 12:00:00 AM
    date issued2022
    identifier issn2332-8983
    identifier otherners_009_02_021403.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4288381
    description abstractVoid fraction is one of the most important parameters that affect two-phase flow heat transfer and pressure drop. In this paper, a commercial gamma densitometer and a high-speed X-ray radiography system developed at the University of Michigan (UM) are used to measure the void fraction in two-phase boiling flows, with water as the working fluid, in a tubular test section. The test section is made of Incoloy 800H/HT with a total length of 1.589 m, an inner diameter of 12.95 mm, and a wall thickness of 3.05 mm. These two instrumentation systems are installed on a traversing platform that travels along the vertical test section to perform measurements at multiple elevations. Subcooled flow boiling and natural convection boiling experiments are performed to measure the void fraction in the test section. Flow visualization images are obtained for bubbly and slug flows from the X-ray radiography system. The wall temperature of the test section is measured at 17 elevations by thermocouples. In addition to the experiments, a multiphase computational fluid dynamics (MCFD) model is developed using ansysfluent to simulate the subcooled flow boiling. The measured wall temperature and void fraction from the experiments are compared with the MCFD simulation results. The root-mean-square (RMS) relative deviations are 3.6% and 16.1% for the wall temperature and void fraction, respectively, between the experimental data and MCFD simulations.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleVoid Fraction Measurement and Prediction of Two-Phase Boiling Flows in a Tubular Test Section
    typeJournal Paper
    journal volume9
    journal issue2
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4055002
    journal fristpage21403
    journal lastpage21403_12
    page12
    treeJournal of Nuclear Engineering and Radiation Science:;2022:;volume( 009 ):;issue: 002
    contenttypeFulltext
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