Comparative study on protective Cr coatings on nuclear fuel cladding Zirlo substrates by AIP and HiPIMS techniques
Author:
Publisher
Elsevier BV
Subject
Materials Chemistry,Surfaces, Coatings and Films,Process Chemistry and Technology,Ceramics and Composites,Electronic, Optical and Magnetic Materials
Reference31 articles.
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2. Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors;Brachet;J. Nucl. Mater.,2019
3. An interesting oxidation phenomenon of Cr coatings on Zry-4 substrates in high temperature steam environment;Han;Corrosion Sci.,2019
4. A high oxidation resistance Ti2AlC coating on Zirlo substrates for loss-of-coolant accident conditions;Li;Ceram. Int.,2019
5. Coating SiC on Zircaloy-4 by magnetron sputtering at room temperature, J. Alloy;Bao;Compd,2017
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1. The hydrogen-helium-vacancy interaction and hydrogen-vacancy clusters formation mechanisms in chromium: A first-principles study;Journal of Nuclear Materials;2024-12
2. Study of irradiation temperature effect on radiation-induced polymorphic transformation mechanisms in ZrO2 ceramics;Optical Materials;2024-10
3. Tailored high-temperature corrosion behavior of Cr coatings using high power impulse magnetron sputtering on ZIRLO alloys for accident-tolerant fuel application;Surface and Coatings Technology;2024-07
4. Oxidation resistance of Mo/Cr bilayer coating on Zr alloy in a 1200 °C steam environment;Corrosion Communications;2024-06
5. Ultra-High Resistance to Electrochemical and High-Temperature Steam Corrosion of Mao/Cr Bilayer Coatings Fabricated on Zr Alloys;2023
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