Oxygen diffusion model of the mixed (U,Pu)O2 ± x: Assessment and application

被引：11
|
作者：
Moore, Emily [1 ]
Gueneau, Christine [1 ]
Crocombette, Jean-Paul [2 ]
机构：
[1] Univ Paris Saclay, CEA, Den Serv Corros & Comportement Mat Leur Environm, F-91191 Gif Sur Yvette, France
[2] Univ Paris Saclay, CEA, Den Serv Rech Met Phys SRMP, F-91191 Gif Sur Yvette, France
来源：
JOURNAL OF NUCLEAR MATERIALS | 2017年 / 485卷
关键词：
CHEMICAL DIFFUSION; PLUTONIUM OXIDE; SELF-DIFFUSION; URANIUM; KINETICS; DEFECTS; PUO2-X; FUELS;
D O I：
10.1016/j.jnucmat.2016.12.026
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The uranium-plutonium (U,Pu)O-2 mixed oxide (MOX) is used as a nuclear fuel in some light water reactors and considered for future reactor generations. To gain insight into fuel restructuring, which occurs during the fuel lifetime as well as possible accident scenarios understanding of the thermodynamic and kinetic behavior is crucial. A comprehensive evaluation of thermo-kinetic properties is incorporated in a computational CALPHAD type model. The present DICTRA based model describes oxygen diffusion across the whole range of plutonium, uranium and oxygen compositions and temperatures by incorporating vacancy and interstitial migration pathways for oxygen. The self and chemical diffusion coefficients are assessed for the binary UO2 x and PuO2 _ (X) systems and the description is extended to the ternary mixed oxide (U,Pu)O-2 +/- x by extrapolation. A simulation to validate the applicability of this model is considered. (C) 2016 Elsevier B.V. All rights reserved.
引用
收藏
页码：216 / 230
页数：15
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