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    Multiphysics Modeling of Pressurized Water Reactor Fuel Performance

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 003::page 31008
    Author:
    Zhu, Wang
    ,
    Chungyu, Zhang
    ,
    Cenxi, Yuan
    DOI: 10.1115/1.4039848
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Nuclear fuel rods operate under complex radioactive, thermal, and mechanical conditions. Nowadays, fuel rod codes usually make great simplifications on analyzing the multiphysics behavior of fuel rods. The present study develops a three-dimensional (3D) module within the framework of a general-purpose finite element solver, i.e., abaqus, for modeling the major physics of the fuel rods. A typical fuel rod, subjected to stable operations and transient conditions, is modeled. The results show that the burnup levels have an important influence on the thermomechanical behavior of fuel rods. The swelling of fission products causes a dramatically increasing strain of pellets. The variation of the stress and the radial displacement of the cladding along the axial direction can be reasonably predicted. It is shown that a quick power ramp or a reactivity insertion accident can induce high tensile stress in the outer regime of the pellet and may cause further fragmentation to the pellets. Fission products migration effects and differential thermal expansion become more severe if there are flaws or imperfections on the pellet.
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      Multiphysics Modeling of Pressurized Water Reactor Fuel Performance

    URI
    https://yetl.yabesh.ir/yetl1/handle/yetl/4252646
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorZhu, Wang
    contributor authorChungyu, Zhang
    contributor authorCenxi, Yuan
    date accessioned2019-02-28T11:05:53Z
    date available2019-02-28T11:05:53Z
    date copyright5/16/2018 12:00:00 AM
    date issued2018
    identifier issn2332-8983
    identifier otherners_004_03_031008.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252646
    description abstractNuclear fuel rods operate under complex radioactive, thermal, and mechanical conditions. Nowadays, fuel rod codes usually make great simplifications on analyzing the multiphysics behavior of fuel rods. The present study develops a three-dimensional (3D) module within the framework of a general-purpose finite element solver, i.e., abaqus, for modeling the major physics of the fuel rods. A typical fuel rod, subjected to stable operations and transient conditions, is modeled. The results show that the burnup levels have an important influence on the thermomechanical behavior of fuel rods. The swelling of fission products causes a dramatically increasing strain of pellets. The variation of the stress and the radial displacement of the cladding along the axial direction can be reasonably predicted. It is shown that a quick power ramp or a reactivity insertion accident can induce high tensile stress in the outer regime of the pellet and may cause further fragmentation to the pellets. Fission products migration effects and differential thermal expansion become more severe if there are flaws or imperfections on the pellet.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleMultiphysics Modeling of Pressurized Water Reactor Fuel Performance
    typeJournal Paper
    journal volume4
    journal issue3
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4039848
    journal fristpage31008
    journal lastpage031008-8
    treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 003
    contenttypeFulltext
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