• Title of article

    Thermal conductivity evaluation of high burnup mixed-oxide (MOX) fuel pellet

  • Author/Authors

    Amaya، نويسنده , , Masaki and Nakamura، نويسنده , , Jinichi and Nagase، نويسنده , , Fumihisa and Fuketa، نويسنده , , Toyoshi، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2011
  • Pages
    6
  • From page
    303
  • To page
    308
  • Abstract
    The thermal conductivity formula of fuel pellet which contains the effects of burnup and plutonium (Pu) addition was proposed based on the Klemens’ theory and reported thermal conductivities of unirradiated (U, Pu) O2 and irradiated UO2 pellets. The thermal conductivity of high burnup MOX pellet was formulated by applying a summation rule between phonon scattering parameters which show the effects of plutonium addition and burnup. Temperature of high burnup MOX fuel was evaluated based on the thermal conductivity integral which was calculated from the above-mentioned thermal conductivity formula. Calculated fuel temperatures were plotted against the linear heat rates of the fuel rods, and were compared with the fuel temperatures measured in a test reactor. Since both values agreed well, it was confirmed that the proposed thermal conductivity formula of MOX pellets is adequate.
  • Journal title
    Journal of Nuclear Materials
  • Serial Year
    2011
  • Journal title
    Journal of Nuclear Materials
  • Record number

    1362579