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    Xenon Behavior in Molten Salt Reactor Graphite

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 004::page 041303-1
    Author:
    Price, Terry J.
    ,
    Chvala, Ondrej
    ,
    Taylor, Zack
    DOI: 10.1115/1.4046356
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This article discusses the aspects of 135Xe behavior in molten salt reactor (MSR) graphite. Models of MSR graphite are described. The related mass transfer and mass diffusion coefficients are described and means by which they can be calculated are detailed. Xenon reactivity effects are explored. A method is presented to model the internal xenon distribution within the graphite stringers.
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      Xenon Behavior in Molten Salt Reactor Graphite

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4275248
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorPrice, Terry J.
    contributor authorChvala, Ondrej
    contributor authorTaylor, Zack
    date accessioned2022-02-04T22:16:47Z
    date available2022-02-04T22:16:47Z
    date copyright6/3/2020 12:00:00 AM
    date issued2020
    identifier issn2332-8983
    identifier otherners_006_04_041303.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4275248
    description abstractThis article discusses the aspects of 135Xe behavior in molten salt reactor (MSR) graphite. Models of MSR graphite are described. The related mass transfer and mass diffusion coefficients are described and means by which they can be calculated are detailed. Xenon reactivity effects are explored. A method is presented to model the internal xenon distribution within the graphite stringers.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleXenon Behavior in Molten Salt Reactor Graphite
    typeJournal Paper
    journal volume6
    journal issue4
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4046356
    journal fristpage041303-1
    journal lastpage041303-7
    page7
    treeJournal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 004
    contenttypeFulltext
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