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    Development of Analysis Tools for Heat Pipes Used in Small Modular Reactors: Sodium Property Correlations

    Source: Journal of Nuclear Engineering and Radiation Science:;2023:;volume( 010 ):;issue: 002::page 20801-1
    Author:
    Beuthe, Thomas
    ,
    Vasić, Aleksandar
    ,
    Azih, Chukwudi
    ,
    Maqueo, Pablo D. G.
    DOI: 10.1115/1.4063112
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Advanced small modular reactors strive to improve reactor safety through increased utilization of passive heat transport and safety systems. An innovative means of meeting this design goal is to use alkali metal heat pipes to cool the reactor under both normal and abnormal operating conditions. A heat pipe model has been added to the ARIANT thermalhydraulic code to enable reactor modeling and support the design and licensing of new reactors. Saturation fluid properties are a fundamental input to this model. Consequently, this article provides a comprehensive comparative overview of the best available sodium saturation property correlations developed over the past century. The results show most of the sodium property correlations needed to model a heat pipe are relatively well-defined and recommendations for their use can be provided.
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      Development of Analysis Tools for Heat Pipes Used in Small Modular Reactors: Sodium Property Correlations

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4295737
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorBeuthe, Thomas
    contributor authorVasić, Aleksandar
    contributor authorAzih, Chukwudi
    contributor authorMaqueo, Pablo D. G.
    date accessioned2024-04-24T22:42:52Z
    date available2024-04-24T22:42:52Z
    date copyright10/20/2023 12:00:00 AM
    date issued2023
    identifier issn2332-8983
    identifier otherners_010_02_020801.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4295737
    description abstractAdvanced small modular reactors strive to improve reactor safety through increased utilization of passive heat transport and safety systems. An innovative means of meeting this design goal is to use alkali metal heat pipes to cool the reactor under both normal and abnormal operating conditions. A heat pipe model has been added to the ARIANT thermalhydraulic code to enable reactor modeling and support the design and licensing of new reactors. Saturation fluid properties are a fundamental input to this model. Consequently, this article provides a comprehensive comparative overview of the best available sodium saturation property correlations developed over the past century. The results show most of the sodium property correlations needed to model a heat pipe are relatively well-defined and recommendations for their use can be provided.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleDevelopment of Analysis Tools for Heat Pipes Used in Small Modular Reactors: Sodium Property Correlations
    typeJournal Paper
    journal volume10
    journal issue2
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4063112
    journal fristpage20801-1
    journal lastpage20801-19
    page19
    treeJournal of Nuclear Engineering and Radiation Science:;2023:;volume( 010 ):;issue: 002
    contenttypeFulltext
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