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    Influence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 003::page 31003
    Author:
    Gaus-Liu, X.
    ,
    Miassoedov, A.
    DOI: 10.1115/1.4035853
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This study investigates heat transfer characters of a volumetrically heated melt pool in LWR lower plenum. Experimental restrictions on prediction reliability are discussed. These restrictions include cooling boundary conditions, vessel geometries, and simulant melt selection on general and localized heat transfer. A survey of existing heat transfer correlations derived from individual experimental definitions is presented. The inconsistency in parameter definitions in Nu–Ra correlations is discussed. Furthermore, the discrepancy of upward Nu depending on the existence of crust is stressed. Several serials of experiments with different combinations boundary condition of external cooling and top cooling were performed in LIVE3D and LIVE2D facilities. The experiments were conducted with simulants with and without crust formation. The influences of cooling boundary conditions, the vessel geometry, and the simulant material on overall heat transfer as well as on heat flux distribution are analyzed. This paper provides own explanations about the discrepancies among the exiting heat transfer correlations and recommends the most suitable descriptions of melt pool heat transfer under different accident management strategies.
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      Influence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4235342
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorGaus-Liu, X.
    contributor authorMiassoedov, A.
    date accessioned2017-11-25T07:18:42Z
    date available2017-11-25T07:18:42Z
    date copyright2017/25/5
    date issued2017
    identifier issn2332-8983
    identifier otherners_003_03_031003.pdf
    identifier urihttp://138.201.223.254:8080/yetl1/handle/yetl/4235342
    description abstractThis study investigates heat transfer characters of a volumetrically heated melt pool in LWR lower plenum. Experimental restrictions on prediction reliability are discussed. These restrictions include cooling boundary conditions, vessel geometries, and simulant melt selection on general and localized heat transfer. A survey of existing heat transfer correlations derived from individual experimental definitions is presented. The inconsistency in parameter definitions in Nu–Ra correlations is discussed. Furthermore, the discrepancy of upward Nu depending on the existence of crust is stressed. Several serials of experiments with different combinations boundary condition of external cooling and top cooling were performed in LIVE3D and LIVE2D facilities. The experiments were conducted with simulants with and without crust formation. The influences of cooling boundary conditions, the vessel geometry, and the simulant material on overall heat transfer as well as on heat flux distribution are analyzed. This paper provides own explanations about the discrepancies among the exiting heat transfer correlations and recommends the most suitable descriptions of melt pool heat transfer under different accident management strategies.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleInfluence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head
    typeJournal Paper
    journal volume3
    journal issue3
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4035853
    journal fristpage31003
    journal lastpage031003-11
    treeJournal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 003
    contenttypeFulltext
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    DSpace software copyright © 2002-2015  DuraSpace
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