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    A New Approach to Generalization of Experimental Data on Heat Transfer to Fluids in Supercritical Region

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 002
    Author:
    Deev, V. I.
    ,
    Kharitonov, V. S.
    ,
    Baisov, A. M.
    ,
    Churkin, A. N.
    DOI: 10.1115/1.4046112
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The paper contains the results of analysis of heat transfer regimes in the case of forced turbulent flow of water and modeling fluids in channels of various configurations at supercritical pressures. Two new complex criteria were proposed for describing heat transfer in the pseudo-phase transition region. A system of equations suitable for the engineering calculation of heat transfer in fuel assemblies of nuclear supercritical water reactors is presented. A comparison of the calculations of heat transfer coefficient (HTC) with experimental data for the regimes of normal, deteriorated and mixed heat transfer is made.
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      A New Approach to Generalization of Experimental Data on Heat Transfer to Fluids in Supercritical Region

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4273675
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    contributor authorDeev, V. I.
    contributor authorKharitonov, V. S.
    contributor authorBaisov, A. M.
    contributor authorChurkin, A. N.
    date accessioned2022-02-04T14:26:50Z
    date available2022-02-04T14:26:50Z
    date copyright2020/02/24/
    date issued2020
    identifier issn2332-8983
    identifier otherners_006_02_021109.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4273675
    description abstractThe paper contains the results of analysis of heat transfer regimes in the case of forced turbulent flow of water and modeling fluids in channels of various configurations at supercritical pressures. Two new complex criteria were proposed for describing heat transfer in the pseudo-phase transition region. A system of equations suitable for the engineering calculation of heat transfer in fuel assemblies of nuclear supercritical water reactors is presented. A comparison of the calculations of heat transfer coefficient (HTC) with experimental data for the regimes of normal, deteriorated and mixed heat transfer is made.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleA New Approach to Generalization of Experimental Data on Heat Transfer to Fluids in Supercritical Region
    typeJournal Paper
    journal volume6
    journal issue2
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4046112
    page21109
    treeJournal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 002
    contenttypeFulltext
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