Low temperature (< 300 °c) oxidation of Zircaloy-2 in water
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference15 articles.
1. Electrochemical Measurements of Corrosion Rates on Zirconium and Zircaloy-2 at Elevated Temperatures
2. Electrochemical Measurements on Zirconium and Zircaloy-2 at Elevated Temperatures
3. The Oxidation and Corrosion of Zirconium and its Alloys
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1. TEM/STEM study of Zircaloy-2 with protective FeAl(Cr) layers under simulated BWR environment and high-temperature steam exposure;Journal of Nuclear Materials;2018-04
2. Hydrogen Pickup Mechanism in Zirconium Alloys;Zirconium in the Nuclear Industry: 18th International Symposium;2018-01-01
3. The coupled current charge compensation model for zirconium alloy fuel cladding oxidation: I. Parabolic oxidation of zirconium alloys;Corrosion Science;2015-11
4. Quantitative measurement of displacement and strain fields in the ZrO2 layer during the transition to nodular oxidation;Corrosion Science;2013-04
5. Examination of the chemical composition of irradiated zirconium based fuel claddings at the metal/oxide interface by TEM;Journal of Nuclear Materials;2010-04
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