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    Effect of Radial Neutron Reflector on the Characteristics of Nuclear Fuel Burn-Up Wave in a Fast Neutron Energy Spectrum Multiplying Medium: A Consistent Parametric Approach

    Source: Journal of Nuclear Engineering and Radiation Science:;2024:;volume( 010 ):;issue: 004::page 41501-1
    Author:
    Ray, Dipanjan
    ,
    Saraswat, Satya Prakash
    ,
    Bhadouria, Vikesh Singh
    DOI: 10.1115/1.4065893
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The influence of radial neutron reflector on the build-up and propagation of a nuclear fuel burn-up wave in a fast multiplying medium is investigated using a consistent parametric approach. Coupled multigroup neutron diffusion equations with a burn-up evolution model are simulated on the two-dimensional cylindrical reactor geometry with azimuthal symmetry. Uranium–plutonium transmutation model is considered, and the simulation is performed by using the finite element multiphysics software package comsol. Transient characteristics of the burn-up wave are represented by two new parameters, namely, transient time (TT) and transient length (TL). TT and TL are defined as the time and distance required for the burn-up wave to attain its steady-state nature. Steady-state phases are characterized in terms of wave velocity, full width half maximum (FWHM), and full width 10% of maximum (FW10M). A sensitivity study of steady-state and transient parameters is conducted for the different values of radial reflector thickness. The potential relevance of these characterization parameters on the development of optimal geometrical configuration of radial neutron reflector in breed and burn (B&B)-based reactor design is addressed based on the sensitivity study.
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      Effect of Radial Neutron Reflector on the Characteristics of Nuclear Fuel Burn-Up Wave in a Fast Neutron Energy Spectrum Multiplying Medium: A Consistent Parametric Approach

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4303611
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    contributor authorRay, Dipanjan
    contributor authorSaraswat, Satya Prakash
    contributor authorBhadouria, Vikesh Singh
    date accessioned2024-12-24T19:15:53Z
    date available2024-12-24T19:15:53Z
    date copyright7/16/2024 12:00:00 AM
    date issued2024
    identifier issn2332-8983
    identifier otherners_010_04_041501.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4303611
    description abstractThe influence of radial neutron reflector on the build-up and propagation of a nuclear fuel burn-up wave in a fast multiplying medium is investigated using a consistent parametric approach. Coupled multigroup neutron diffusion equations with a burn-up evolution model are simulated on the two-dimensional cylindrical reactor geometry with azimuthal symmetry. Uranium–plutonium transmutation model is considered, and the simulation is performed by using the finite element multiphysics software package comsol. Transient characteristics of the burn-up wave are represented by two new parameters, namely, transient time (TT) and transient length (TL). TT and TL are defined as the time and distance required for the burn-up wave to attain its steady-state nature. Steady-state phases are characterized in terms of wave velocity, full width half maximum (FWHM), and full width 10% of maximum (FW10M). A sensitivity study of steady-state and transient parameters is conducted for the different values of radial reflector thickness. The potential relevance of these characterization parameters on the development of optimal geometrical configuration of radial neutron reflector in breed and burn (B&B)-based reactor design is addressed based on the sensitivity study.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleEffect of Radial Neutron Reflector on the Characteristics of Nuclear Fuel Burn-Up Wave in a Fast Neutron Energy Spectrum Multiplying Medium: A Consistent Parametric Approach
    typeJournal Paper
    journal volume10
    journal issue4
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4065893
    journal fristpage41501-1
    journal lastpage41501-14
    page14
    treeJournal of Nuclear Engineering and Radiation Science:;2024:;volume( 010 ):;issue: 004
    contenttypeFulltext
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