Materials interactions during high temperature transients: Discussion about the use of the kinetic rate constants in Zircaloy oxidation
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference27 articles.
1. The Metallurgy of Zr;Douglass,1971
2. Comprehensive presentation of extended Zircaloy-4 steam oxidation results 600–1600°C;Leistikow,1983
3. Simulation with the HITO code of the interaction of Zircaloy with uranium dioxide and steam at high temperatures
4. The O−Zr (Oxygen-Zirconium) system
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1. Determination of dose rate effects on Zircaloy oxidation using proton irradiation and oxygen transport modeling;Journal of Nuclear Materials;2019-09
2. Multilayer interface tracking model of zirconium clad oxidation;Journal of Nuclear Materials;2018-10
3. The effect of high pressure steam on the oxidation of low-Sn Zircaloy-4 at temperatures between 700 and 900°C;Journal of Nuclear Materials;2012-01
4. Percolation Processes in a Network of Grain Boundaries in Ultrafine-Grained Materials;Superplasticity and Grain Boundaries in Ultrafine-Grained Materials;2011
5. Diffusion model for the oxidation of Zircaloy-4 at 400°C in steam. The influence of metallurgical structure (precipitates and grain size);Journal of Nuclear Materials;1999-07
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