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    Investigation of Natural Convection in Heat Generating Molten Nuclear Fuel and Assessment of Core Damage Propagation

    Source: Journal of Thermal Science and Engineering Applications:;2015:;volume( 007 ):;issue: 003::page 31009
    Author:
    Ravi, L.
    ,
    Velusamy, K.
    ,
    Chellapandi, P.
    DOI: 10.1115/1.4030248
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Total instantaneous blockage (TIB) is a severe subassembly accident in a sodium cooled fast reactor. During such an accident, a heat generating fuel pool is formed which is bounded by six neighboring subassemblies which are forcecooled by sodium. The molten fuel pool attacks the walls of the neighboring hexcan, melting them layer by layer. The rate of propagation of such damage and the temperature rise in sodium due to heat transfer from fuel pool through hexcan wall are investigated by a twostep mathematical approach. In the first step, natural convection in the fuel pool is studied by a 2D axisymmetric computational fluid dynamic model and correlations for effective conductivity as a function of internal Rayleigh number and aspect ratio have been developed. In the second step, rate of damage propagation to the hexcan wall and sodium temperature rise are predicted by a 1D transient enthalpy model. It is found that rate of damage propagation is accelerated by natural convection inside the pool. Further, the rate of heat transfer to neighboring subassembly sodium also increases due to natural convection in the pool. Eventually, the residual thickness of hexcan at the time of reactor trip is found to be insensitive to the presence/absence of natural convection in the pool.
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      Investigation of Natural Convection in Heat Generating Molten Nuclear Fuel and Assessment of Core Damage Propagation

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    http://yetl.yabesh.ir/yetl1/handle/yetl/159729
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    contributor authorRavi, L.
    contributor authorVelusamy, K.
    contributor authorChellapandi, P.
    date accessioned2017-05-09T01:23:50Z
    date available2017-05-09T01:23:50Z
    date issued2015
    identifier issn1948-5085
    identifier othertsea_007_03_031009.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/159729
    description abstractTotal instantaneous blockage (TIB) is a severe subassembly accident in a sodium cooled fast reactor. During such an accident, a heat generating fuel pool is formed which is bounded by six neighboring subassemblies which are forcecooled by sodium. The molten fuel pool attacks the walls of the neighboring hexcan, melting them layer by layer. The rate of propagation of such damage and the temperature rise in sodium due to heat transfer from fuel pool through hexcan wall are investigated by a twostep mathematical approach. In the first step, natural convection in the fuel pool is studied by a 2D axisymmetric computational fluid dynamic model and correlations for effective conductivity as a function of internal Rayleigh number and aspect ratio have been developed. In the second step, rate of damage propagation to the hexcan wall and sodium temperature rise are predicted by a 1D transient enthalpy model. It is found that rate of damage propagation is accelerated by natural convection inside the pool. Further, the rate of heat transfer to neighboring subassembly sodium also increases due to natural convection in the pool. Eventually, the residual thickness of hexcan at the time of reactor trip is found to be insensitive to the presence/absence of natural convection in the pool.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleInvestigation of Natural Convection in Heat Generating Molten Nuclear Fuel and Assessment of Core Damage Propagation
    typeJournal Paper
    journal volume7
    journal issue3
    journal titleJournal of Thermal Science and Engineering Applications
    identifier doi10.1115/1.4030248
    journal fristpage31009
    journal lastpage31009
    identifier eissn1948-5093
    treeJournal of Thermal Science and Engineering Applications:;2015:;volume( 007 ):;issue: 003
    contenttypeFulltext
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