Multilayer interface tracking model of zirconium clad oxidation

JOURNAL OF NUCLEAR MATERIALS

卷:509

Article

Reyes, Michael¹  Aryanfar, Asghar^2,3  Baek, Sun Woong¹  Marian, Jaime^1,3 

[1] Univ Calif Los Angeles, Dept Mech & Aerosp Engn, Los Angeles, CA 90095 USA

[2] Bahcesehir Int Univ, Civil Mech & Energy Engn, Istanbul, Turkey

[3] Univ Calif Los Angeles, Dept Mat Sci & Engn, Los Angeles, CA 90095 USA

关键词: Zirconium oxide;    Zircalloy clad;    Zircalloy corrosion;    Oxidation;    Nuclear reactor;   

DOI  :  10.1016/j.jnucmat.2018.07.025

来源: Elsevier

【 摘 要 】

We present a numerical model to predict oxide scale growth and failure in zirconium clad exposed to water in out-of-pile conditions. The model includes the formation of two oxide sublayers on top of the metal clad, whose interfaces are tracked using a Stefan model coupled to diffusion kinetics. The kinetics is coupled to a thermal model that accounts for temperature gradient effects via thermo-migration inside the clad. The model also includes a mechanical failure criterion based on the accumulation of compressive stresses in the oxide near the interface with the metal. We present results of oxygen diffusion into the clad, oxide formation as a function of time, and oxide fragmentation by mechanical failure. We find that the growth of the oxide scale as the cubic root of time is recovered for a special charge distribution near the oxide interface. This charge distribution can be suppressed via alloying, which explains the square root scaling for certain Zr alloys. A sensitivity study has been conducted, showing that variations of +/- 15% in selected model parameters result in approximately +/- 5% changes in model predictions. (C) 2018 Elsevier B.V. All rights reserved.

【 授权许可】

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