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    Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)

    Source: Journal of Nuclear Engineering and Radiation Science:;2021:;volume( 008 ):;issue: 001::page 11324-1
    Author:
    Hering, Wolfgang
    ,
    Fuchs, Joachim
    ,
    Onea, Alexandru
    ,
    Perez-Martin, Sara
    ,
    Schaub, Thomas
    DOI: 10.1115/1.4052642
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The experimental liquid metal loops hosted within the Karlsruhe Sodium laboratory (KASOLA) comprise a set of facilities to study liquid metal flows for various types of energy applications ranging from room temperature conditions used for education and training and fundamental research up to challenges posed by multiphysics problems such as material–fluid interactions at high temperatures. Extreme conditions, such as sodium boiling, relevant to thermo-electric conversion or fast reactor safety are covered in a dedicated small-scale facility (Karlsruhe receiver test facility (KARIFA)). The complete experimental range is complemented by system code support and computational fluid dynamics (CFD) simulation. The outcome of the experiments is used for code validation and development allowing application not only on component but also on system level. The paper presents main experimental facilities and supporting computational codes used at KASOLA.
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      Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)

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    https://yetl.yabesh.ir/yetl1/handle/yetl/4284018
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorHering, Wolfgang
    contributor authorFuchs, Joachim
    contributor authorOnea, Alexandru
    contributor authorPerez-Martin, Sara
    contributor authorSchaub, Thomas
    date accessioned2022-05-08T08:30:40Z
    date available2022-05-08T08:30:40Z
    date copyright12/7/2021 12:00:00 AM
    date issued2021
    identifier issn2332-8983
    identifier otherners_008_01_011324.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4284018
    description abstractThe experimental liquid metal loops hosted within the Karlsruhe Sodium laboratory (KASOLA) comprise a set of facilities to study liquid metal flows for various types of energy applications ranging from room temperature conditions used for education and training and fundamental research up to challenges posed by multiphysics problems such as material–fluid interactions at high temperatures. Extreme conditions, such as sodium boiling, relevant to thermo-electric conversion or fast reactor safety are covered in a dedicated small-scale facility (Karlsruhe receiver test facility (KARIFA)). The complete experimental range is complemented by system code support and computational fluid dynamics (CFD) simulation. The outcome of the experiments is used for code validation and development allowing application not only on component but also on system level. The paper presents main experimental facilities and supporting computational codes used at KASOLA.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleExperiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)
    typeJournal Paper
    journal volume8
    journal issue1
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4052642
    journal fristpage11324-1
    journal lastpage11324-13
    page13
    treeJournal of Nuclear Engineering and Radiation Science:;2021:;volume( 008 ):;issue: 001
    contenttypeFulltext
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    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
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