• Title of article

    Thermodynamic investigations of ThO2–UO2 solid solutions

  • Author/Authors

    Dash، نويسنده , , Smruti and Parida، نويسنده , , S.C and Singh، نويسنده , , Ziley and Sen، نويسنده , , B.K. and Venugopal، نويسنده , , V.، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2009
  • Pages
    15
  • From page
    267
  • To page
    281
  • Abstract
    Heat capacities and enthalpy increments of solid solutions Th1−yUyO2(s) (y = 0.0196, 0.0392, 0.0588, 0.098, 0.1964) and Simfuel (y = 0.0196) were measured by using a differential scanning calorimeter and a high temperature drop calorimeter. The heat capacities were measured in two temperature ranges: 127–305 K and 305–845 K and enthalpy increments were determined in the temperature range 891–1698 K. A heat capacity expression as a function of uranium content y and temperature and a set of self-consistent thermodynamic functions for Th1−yUyO2(s) were computed from present work and the literature data. The oxygen potentials of Th1−yUyO2+x(s) have been calculated and expressed as a polynomial functions of uranium content y, excess oxygen x and temperature T. The phase diagram, oxygen potential diagram of thorium–uranium–oxygen system and major vapour species over urania thoria mixed oxide have been computed using FactSage code.
  • Journal title
    Journal of Nuclear Materials
  • Serial Year
    2009
  • Journal title
    Journal of Nuclear Materials
  • Record number

    1365114