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    Temperature Distribution Inside Fresh Fuel Pins of Pressure Tube Supercritical Water Cooled Reactor

    Source: Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 001::page 11008
    Author:
    Kovaltchouk, Vitali
    ,
    Nichita, Eleodor
    ,
    Saltanov, Eugene
    DOI: 10.1115/1.4031163
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The radial temperature profile for ThO2PuO2 freshfuel pins of the pressuretube supercriticalwatercooled reactor (PTSCWR) is simulated for two different radial distributions of the ThO2 and PuO2, one whereby the ThO2 and PuO2 are mixed together in a single, homogeneous region, and another one whereby ThO2 and PuO2 occupy separate radial regions inside the pin with the ThO2 occupying the inner region. The radial power density in each fuel pin is calculated from a latticelevel transport calculation using the lattice code DRAGON and is used together with the temperaturedependent fuel thermal conductivity to analytically solve the heat conduction equation and thus calculate the temperature profile inside the fuel pin. Results indicate that, for fresh fuel, the centerline temperature is much lower for a tworegion pin than for a singleregion pin, and thus, the risk of fuel melting is greatly reduced for the tworegion fuel compared to the singleregion fuel.
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      Temperature Distribution Inside Fresh Fuel Pins of Pressure Tube Supercritical Water Cooled Reactor

    URI
    http://yetl.yabesh.ir/yetl1/handle/yetl/162185
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorKovaltchouk, Vitali
    contributor authorNichita, Eleodor
    contributor authorSaltanov, Eugene
    date accessioned2017-05-09T01:32:10Z
    date available2017-05-09T01:32:10Z
    date issued2016
    identifier issn2332-8983
    identifier otherNERS_2_1_011008.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/162185
    description abstractThe radial temperature profile for ThO2PuO2 freshfuel pins of the pressuretube supercriticalwatercooled reactor (PTSCWR) is simulated for two different radial distributions of the ThO2 and PuO2, one whereby the ThO2 and PuO2 are mixed together in a single, homogeneous region, and another one whereby ThO2 and PuO2 occupy separate radial regions inside the pin with the ThO2 occupying the inner region. The radial power density in each fuel pin is calculated from a latticelevel transport calculation using the lattice code DRAGON and is used together with the temperaturedependent fuel thermal conductivity to analytically solve the heat conduction equation and thus calculate the temperature profile inside the fuel pin. Results indicate that, for fresh fuel, the centerline temperature is much lower for a tworegion pin than for a singleregion pin, and thus, the risk of fuel melting is greatly reduced for the tworegion fuel compared to the singleregion fuel.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleTemperature Distribution Inside Fresh Fuel Pins of Pressure Tube Supercritical Water Cooled Reactor
    typeJournal Paper
    journal volume2
    journal issue1
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4031163
    journal fristpage11008
    journal lastpage11008
    treeJournal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 001
    contenttypeFulltext
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