Title of article
A review of the thermophysical properties of MOX and UO2 fuels
Author/Authors
Carbajo، نويسنده , , Juan J and Yoder، نويسنده , , Gradyon L and Popov، نويسنده , , Sergey G and Ivanov، نويسنده , , Victor K، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2001
Pages
18
From page
181
To page
198
Abstract
A critical review of the thermophysical properties of UO2 and MOX fuels has been completed, and the best correlations for thermophysical properties have been selected. The properties reviewed are solidus and liquidus temperatures of the uranium/plutonium dioxide system (melting and solidification temperatures), thermal expansion and density, enthalpy and specific heat, enthalpy (or heat) of fusion, and thermal conductivity. Only fuel properties have been reviewed. The selected set of property correlations was compiled to be used in thermal-hydraulic codes to perform safety calculations.
Journal title
Journal of Nuclear Materials
Serial Year
2001
Journal title
Journal of Nuclear Materials
Record number
1355810
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