Thermodynamic modelling of advanced oxide and carbide nuclear fuels: description of the U-Pu-O-C system
In the present work a thermodynamic model is derived for the (U,Pu)O2 oxide, the (U,Pu)C carbide fuels using the Calphad method to describe consistently both phase diagrams and thermodynamic data of the phase involved in the U-Pu_O_C system. All the available thermodynamic and phase diagram data of the binary and ternary sub-systems are very well reproduced by our model. For the quaternary system, the calculated phase equilibria in the U0.3PU0.7-C-O region are in good agreement with the experimental data.
Keywords:
Nuclear fuels, uranium dioxide, mixed oxide of uranium and plutonium, uranium carbide, plutonium carbide, mixed carbide of uranium and plutoinium, uranium oxycarbide, plutonium oxycarbide, mixed oxycarbide of uranium and plutonium, thermodynamics, phase diagrams, calphad
GUENEAU Christine;
DUPIN N.;
SUNDMAN B.;
MARTIAL Chantal;
DUMAS Jean-Christophe;
GOSSE Stephane;
CHATAIN Sylvie;
DE BRUYCKER Frank;
MANARA Dario;
KONINGS Rudy;
2012-04-19
ELSEVIER SCIENCE BV
JRC65259
0022-3115,
http://adsabs.harvard.edu/abs/2011JNuM..419..145G,
https://publications.jrc.ec.europa.eu/repository/handle/JRC65259,
10.1016/j.jnucmat.2011.07.033,
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