Evolution of Cr/Cr2O3 interface in Cr-coated zirconium alloy in high temperature steam
Author:
Publisher
Elsevier BV
Subject
General Materials Science,General Chemical Engineering,General Chemistry
Reference43 articles.
1. Materials challenges in nuclear energy;Zinkle;Acta Mater.,2013
2. Review of stress fields in Zirconium alloys corrosion scales;Guerain;Corros. Sci.,2015
3. Current status of materials development of nuclear fuel cladding tubes for light water reactors;Duan;Nucl. Eng. Des.,2017
4. A study of the breakaway oxidation behavior of zirconium cladding materials;Kim;J. Nucl. Mater.,2011
5. High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments;Pint;J. Nucl. Mater.,2013
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