Enhanced crud resistance of CrAl coated ATF claddings in simulated PWR conditions
Author:
Funder
National Research Foundation of Korea
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference37 articles.
1. Development status of accident-tolerant fuel for light water reactors in Korea;Kim;Nucl. Eng. Technol.,2016
2. Development of Cr-Al Coating on Zircaloy-4 for Enhanced Accident Tolerant Fuel;Kim,2021
3. Deposition of boron on fuel rod surface under sub-cooled boiling conditions—aAn approach toward understanding AOA occurrence;Uchida;Nucl. Eng. Des.,2011
4. Corrosion characteristics and oxide microstructures of Zircaloy-4 in aqueous alkali hydroxide solutions;Jeong;J. Nucl. Mater.,1999
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1. Fouling behavior on the zircaloy-4 alloy cladding tube: An experimental and simulation study;Applied Surface Science;2024-10
2. Effects of nitrogen content on the phase composition and high-temperature steam oxidation resistance of Cr0.5Al0.5Nx (x = 0.33, 0.81, 1.23) coatings on Zry-4 alloy;Surface and Coatings Technology;2024-07
3. Oxidation behavior of Cr1-xAlx coated Zr-4 alloy under 1200 °C high temperature steam environment;Vacuum;2024-01
4. Inner‐Side‐Protected Cladding with Meter Scale for High‐Temperature Oxidation Resistance via the Swaging–Drawing Process;International Journal of Energy Research;2024-01
5. Dependence of Arc Ion plating process on properties of CrAl coating for ATF cladding: Effect of bias voltage and targets;Journal of Nuclear Materials;2023-10
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