Irradiation resistance of vacuum arc chromium coatings for zirconium alloy fuel claddings
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference30 articles.
1. Accident tolerant fuels for LWRs: a perspective;Zinkle;J. Nucl. Mater.,2014
2. Current status of materials development of nuclear fuel cladding tubes for light water reactors;Duan;Nucl. Eng. Des.,2017
3. Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings;Tang;Corrosion Rev.,2017
4. Accident tolerant fuel cladding development: promise, status, and challenges;Terrani;J. Nucl. Mater.,2018
5. AREVA NP's enhanced accident-tolerant fuel developments: focus on Cr-coated M5 cladding;Bischoff;Nucl. Eng. Technol.,2018
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