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
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