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Article Dans Une Revue Journal of Nuclear Materials Année : 2002

Progress in the thermodynamic modelling of the O–U binary system

Résumé

The fuel of civil nuclear plants, UO2, melts at 3120 K. During an hypothetical severe accident, urania, submitted to high temperatures and various oxygen potentials, presents a wide non-stoichiometry range: the melting temperature of UO2+/-x related to oxygen potential, decreases in all cases. In this scenario, urania could react with other materials, firstly zircaloy, and the melting temperature of (U, Zr)O2+/-x, still decreases. That is why the critical assessment of the O-U binary system including the non-stoichiometry range of urania, is a major step to a correct thermodynamic modelling of multicomponent systems for nuclear safety. The very numerous experimental information has been compiled and analysed. The associate model was used for the liquid phase, and a sublattice model for UO2+/-x; U4O9-x, U3O8 and UO3 were treated as stoichiometric. Phase diagram and thermodynamic properties have been calculated from the optimised Gibbs energy parameters. The calculated consistency with the experimental ones is quite satisfactory. (C) 2002 Published by Elsevier Science B.V.

Domaines

Matériaux

Dates et versions

hal-01895371 , version 1 (15-10-2018)

Identifiants

Citer

Pierre-Yves Chevalier, Evelyne Fischer, Bertrand Cheynet. Progress in the thermodynamic modelling of the O–U binary system. Journal of Nuclear Materials, 2002, 303 (1), pp.1 - 28. ⟨10.1016/S0022-3115(02)00813-9⟩. ⟨hal-01895371⟩

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