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    Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel

    Source: Journal of Nuclear Engineering and Radiation Science:;2023:;volume( 009 ):;issue: 004::page 41104-1
    Author:
    Han, Wenbin
    ,
    Deng, Jian
    ,
    Lu, Qi
    ,
    Chen, Chong
    ,
    Xu, Youyou
    ,
    Zhang, Tao
    ,
    Huang, Shanfang
    DOI: 10.1115/1.4062119
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Additive manufacturing (AM) is a transformational digital manufacturing technology featured with rapidity, customizability, precision, and economy, which is fundamentally altering the way components are designed and manufactured. AM enables the freedom of design, and makes full use of complexity of geometry which “comes for free”. Applying AM technology to nuclear industry can yield advanced reactor designs with function and structure matched for the best thermal, fluidic and mechanical performance. In this work, an AM-informed reactor core design with silicon carbide (SiC) matrix and tri-structural isotropic (TRISO) particle fuel is proposed and analyzed. The core is an integrated 3D-printed SiC bulk with helical cruciform coolant channels, and the UO2-bearing TRISO fuel particles are dispersed in the bulk. A multiphysics analysis framework for irregular geometry is developed to analyze and further optimize the reactor design. The TRISO particle positions are generated with discrete element method (DEM). The Reactor Monte Carlo code (RMC) and the commercial computational fluid dynamics (CFD) software star-ccm+ are used for the neutronic and thermal-fluidic analyses, respectively. RMC simulates the neutron transport to predict the effective multiplication factor and power distribution. star-ccm+ calculates the flow and heat transfer in coolant channels and heat conduction in solid matrix with the power distribution as the heat source. Preliminary results show that the power peaking factor FQ decreases below 1.65, the heat transfer area increases by 30.3% and the fuel peaking temperature decreases by 25 K. The optimized AM-informed design enjoys better neutronic and thermal-fluidic performance than those with regular geometry.
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      Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4294886
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorHan, Wenbin
    contributor authorDeng, Jian
    contributor authorLu, Qi
    contributor authorChen, Chong
    contributor authorXu, Youyou
    contributor authorZhang, Tao
    contributor authorHuang, Shanfang
    date accessioned2023-11-29T19:35:59Z
    date available2023-11-29T19:35:59Z
    date copyright4/17/2023 12:00:00 AM
    date issued4/17/2023 12:00:00 AM
    date issued2023-04-17
    identifier issn2332-8983
    identifier otherners_009_04_041501.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4294886
    description abstractAdditive manufacturing (AM) is a transformational digital manufacturing technology featured with rapidity, customizability, precision, and economy, which is fundamentally altering the way components are designed and manufactured. AM enables the freedom of design, and makes full use of complexity of geometry which “comes for free”. Applying AM technology to nuclear industry can yield advanced reactor designs with function and structure matched for the best thermal, fluidic and mechanical performance. In this work, an AM-informed reactor core design with silicon carbide (SiC) matrix and tri-structural isotropic (TRISO) particle fuel is proposed and analyzed. The core is an integrated 3D-printed SiC bulk with helical cruciform coolant channels, and the UO2-bearing TRISO fuel particles are dispersed in the bulk. A multiphysics analysis framework for irregular geometry is developed to analyze and further optimize the reactor design. The TRISO particle positions are generated with discrete element method (DEM). The Reactor Monte Carlo code (RMC) and the commercial computational fluid dynamics (CFD) software star-ccm+ are used for the neutronic and thermal-fluidic analyses, respectively. RMC simulates the neutron transport to predict the effective multiplication factor and power distribution. star-ccm+ calculates the flow and heat transfer in coolant channels and heat conduction in solid matrix with the power distribution as the heat source. Preliminary results show that the power peaking factor FQ decreases below 1.65, the heat transfer area increases by 30.3% and the fuel peaking temperature decreases by 25 K. The optimized AM-informed design enjoys better neutronic and thermal-fluidic performance than those with regular geometry.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleNeutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel
    typeJournal Paper
    journal volume9
    journal issue4
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4062119
    journal fristpage41104-1
    journal lastpage41104-7
    page7
    treeJournal of Nuclear Engineering and Radiation Science:;2023:;volume( 009 ):;issue: 004
    contenttypeFulltext
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