Breakaway oxidation of zirconium at 573 K
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference14 articles.
1. The kinetics and mechanism of the oxidation of zircaloy-2 at 350–500 °C
2. Transmission electron microscopy of αZrO2 films formed in 573 K oxygen
3. The morphology of thick oxide films on Zircaloy-2
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1. Investigation of breakaway corrosion observed during oxide growth in pure and low alloying element content Zr exposed in water at 360°C;Journal of Nuclear Materials;2022-01
2. Oxygen diffusion kinetics of an advanced three step heat treatment for zirconium alloy ZrNb7;Surface and Coatings Technology;2018-04
3. Microstructural characterization of ZrO2 layers formed during the transition to breakaway oxidation;Journal of Nuclear Materials;2010-04
4. Corrosion behavior of Zr−Nb alloys in 360°C water and 500°C supercritical water;Metals and Materials International;2006-12
5. Oxidation properties of Zr–Nb alloys at 500–600°C under low oxygen potentials;Corrosion Science;2005-02
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