锆基弥散微封装燃料等效传热系数数值模拟研究
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摘要
为研究锆基弥散微封装燃料(M3燃料)的等效传热系数,假定TRISO(三层各向同性)颗粒球在锆基体内呈现体心立方排布,通过ABAQUS软件,基于均匀化理论,建立了M3燃料等效传热系数的模拟方法。依据建立的模拟方法,对不同相体积M3燃料的等效传热系数进行了研究分析。模拟结果显示:等效传热系数会随着温度的升高而升高、随燃耗和相体积的增加而降低。
In order to research the equivalent thermal conductivity coefficient of Zirconium based dispersion micro encapsulated fuel(M3 fuel),in this research,assuming the TRISO(three layer isotropic) particle embedded in the zirconium with body-centered cubic distribution,the simulation method for the equivalent thermal conductivity of M3 fuel is established with the help of ABAQUS software,based on the homogenization theory.The equivalent thermal conductivity coefficients of different phase volume M3 fuel were analyzed with this simulation method.Simulation results show that the equivalent thermal conductivity coefficient increases with the increasing of temperature,and the equivalent thermal conductivity coefficient decreases with the increasing of burnup and phase volume.
In order to research the equivalent thermal conductivity coefficient of Zirconium based dispersion micro encapsulated fuel(M3 fuel),in this research,assuming the TRISO(three layer isotropic) particle embedded in the zirconium with body-centered cubic distribution,the simulation method for the equivalent thermal conductivity of M3 fuel is established with the help of ABAQUS software,based on the homogenization theory.The equivalent thermal conductivity coefficients of different phase volume M3 fuel were analyzed with this simulation method.Simulation results show that the equivalent thermal conductivity coefficient increases with the increasing of temperature,and the equivalent thermal conductivity coefficient decreases with the increasing of burnup and phase volume.
引文
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[3]Hales J D,Williamson R L,Novascone S R,et al.Multidimensional multiphysics simulation of TRISO particle fuel[J].Journal of Nuclear Materials,2013,443(1):531-543.
[4]Mac Donald P E,Thompson L B.MATPRO:a handbook of materials properties for use in the analysis of light water reactor fuel rod behavior[R].SEE CODE-9502158Aerojet Nuclear Co.,Idaho Falls,Idaho(USA).Idaho National Engineering Lab.,1976.
[2]Lucuta P G,Matzke H,Hastings I J.A pragmatic approach to modeling thermal conductivity of irradiated UO2 fuel:review and recommendations[J].Journal of nuclear materials,1996,232(2):166-180.
[3]Hales J D,Williamson R L,Novascone S R,et al.Multidimensional multiphysics simulation of TRISO particle fuel[J].Journal of Nuclear Materials,2013,443(1):531-543.
[4]Mac Donald P E,Thompson L B.MATPRO:a handbook of materials properties for use in the analysis of light water reactor fuel rod behavior[R].SEE CODE-9502158Aerojet Nuclear Co.,Idaho Falls,Idaho(USA).Idaho National Engineering Lab.,1976.