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Article Dans Une Revue Journal of Nuclear Materials Année : 2018

Contribution to the thermodynamic description of the corium - The U-Zr-O system

Résumé

In order to understand the stratification process that may occur in the late phase of the fuel degradation during a severe accident in a PWR, the thermodynamic knowledge of the U-Zr-O system is crucial. The presence of a miscibility gap in the U-Zr-O liquid phase may lead to a stratified configuration, which will impact the accidental scenario management. The aim of this work was to obtain new experimental data in the U-Zr-O liquid miscibility gap. New tie-line data were provided at 2567 +/- 25 K. The related thermodynamic models were reassessed using present data and literature values. The reassessed model will be implemented in the TAF-ID international database. The composition and density of phases potentially formed during stratification will be predicted by coupling current thermodynamic model with thermal-hydraulics codes. (C) 2018 Elsevier B.V. All rights reserved.
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Dates et versions

hal-02067841 , version 1 (14-03-2019)

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A. Quaini, C. Gueneau, S. Gosse, N. Dupin, E. Sundman, et al.. Contribution to the thermodynamic description of the corium - The U-Zr-O system. Journal of Nuclear Materials, 2018, 501, pp.104-131. ⟨10.1016/j.jnucmat.2018.01.023⟩. ⟨hal-02067841⟩
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