• Title of article

    Simulations of heat and oxygen diffusion in UO2 nuclear fuel rods

  • Author/Authors

    Ramirez، نويسنده , , J.C. and Stan، نويسنده , , M. and Cristea، نويسنده , , P.، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2006
  • Pages
    11
  • From page
    174
  • To page
    184
  • Abstract
    We present finite-element simulations of coupled heat and oxygen atom diffusion for UO2 fuel pellets. The expressions for thermal conductivity, specific heat and oxygen diffusivity for the fuel element are obtained directly from previously published correlations, or from analysis of previously published data. We examine the temperature and non-stoichiometry distributions for a varying range of conditions. Simulations are performed for steady-state and transient regime in one-dimensional (purely radial) configurations. For steady-state conditions we perform parametric studies that determine the maximum temperature in the fuel rod as a function of non-stoichiometry and heat generation rate intensity. For transient simulations, we examine the time lag in the response of the temperature and non-stoichiometry distributions with respect to sudden changes in heat generation rate intensity and oxygen removal rate. All simulations are performed with the commercial code COMSOL Multiphysics™.
  • Journal title
    Journal of Nuclear Materials
  • Serial Year
    2006
  • Journal title
    Journal of Nuclear Materials
  • Record number

    1364266