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

被引:35
作者
Quaini, A. [1 ]
Gueneau, C. [1 ]
Gosse, S. [1 ]
Dupin, N. [2 ]
Sundman, B. [3 ]
Brackx, E. [4 ]
Domenger, R. [4 ]
Kurata, M. [5 ]
Hodaj, F. [6 ]
机构
[1] Univ Paris Saclay, CEA, Den Serv Corros & Comportement Mat Leur Environm, F-91191 Gif Sur Yvette, France
[2] Calcul Thermo, F-63670 Orcet, France
[3] Univ Paris Saclay, CEA Saclay, INSTN, F-91191 Gif Sur Yvette, France
[4] CEA, Nucl Energy Div, Res Dept Min & Fuel Recycling Proc, SA2I,LMAC, BP 17171, Bagnols Sur Ceze, France
[5] Japan Atom Energy Agcy, Shirakata Shirane 2-4, Tokai, Ibaraki 3191195, Japan
[6] Univ Grenoble Alpes, CNRS, Grenoble INP, SIMAP, F-38000 Grenoble, France
关键词
MOLTEN ZIRCALOY-4; PHASE-DIAGRAM; ZIRCONIUM ALLOY; HEAT-CAPACITY; DELTA-PHASE; PT-C; TEMPERATURE; UO2; DISSOLUTION; EQUILIBRIA;
D O I
10.1016/j.jnucmat.2018.01.023
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
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.
引用
收藏
页码:104 / 131
页数:28
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