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    A Parametric Study of Fuel Lattice Design for HTR-10

    Source: Journal of Engineering for Gas Turbines and Power:;2011:;volume( 133 ):;issue: 008::page 84503
    Author:
    Meng-Jen Wang
    ,
    Jinn-Jer Peir
    ,
    Chen-Wei Chi
    ,
    Jenq-Horng Liang
    DOI: 10.1115/1.4002879
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In this study, the multiplication factor and neutron spectrum behaviors were investigated against the moderator-to-fuel ratio, the fuel loading height, and the detector location in high-temperature gas-cooled reactor (HTR)-10. The MCNP5 computer code (version 1.51) was employed to perform all the simulation computations. The results revealed that the multiplication factor varies significantly depending on the moderator-to-fuel ratio and the fuel loading height due to the competition among the neutron moderation and absorption abilities of the moderator as well as the neutron production ability of the fuel. Due to its inherent stability, HTR-10 is deliberately designed such that the multiplication factor decreases and the neutron spectrum softens as the moderator-to-fuel ratio increases. The average neutron energy level in the HTR-10 fuel balls is approximately 240 keV and ranges from smallest to largest at the middle, bottom, and top of the reactor core, respectively.
    keyword(s): Fuels , Design , Neutrons AND Spectra (Spectroscopy) ,
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      A Parametric Study of Fuel Lattice Design for HTR-10

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    https://yetl.yabesh.ir/yetl1/handle/yetl/145981
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    contributor authorMeng-Jen Wang
    contributor authorJinn-Jer Peir
    contributor authorChen-Wei Chi
    contributor authorJenq-Horng Liang
    date accessioned2017-05-09T00:43:35Z
    date available2017-05-09T00:43:35Z
    date copyrightAugust, 2011
    date issued2011
    identifier issn1528-8919
    identifier otherJETPEZ-27169#084503_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/145981
    description abstractIn this study, the multiplication factor and neutron spectrum behaviors were investigated against the moderator-to-fuel ratio, the fuel loading height, and the detector location in high-temperature gas-cooled reactor (HTR)-10. The MCNP5 computer code (version 1.51) was employed to perform all the simulation computations. The results revealed that the multiplication factor varies significantly depending on the moderator-to-fuel ratio and the fuel loading height due to the competition among the neutron moderation and absorption abilities of the moderator as well as the neutron production ability of the fuel. Due to its inherent stability, HTR-10 is deliberately designed such that the multiplication factor decreases and the neutron spectrum softens as the moderator-to-fuel ratio increases. The average neutron energy level in the HTR-10 fuel balls is approximately 240 keV and ranges from smallest to largest at the middle, bottom, and top of the reactor core, respectively.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleA Parametric Study of Fuel Lattice Design for HTR-10
    typeJournal Paper
    journal volume133
    journal issue8
    journal titleJournal of Engineering for Gas Turbines and Power
    identifier doi10.1115/1.4002879
    journal fristpage84503
    identifier eissn0742-4795
    keywordsFuels
    keywordsDesign
    keywordsNeutrons AND Spectra (Spectroscopy)
    treeJournal of Engineering for Gas Turbines and Power:;2011:;volume( 133 ):;issue: 008
    contenttypeFulltext
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