Oxidation kinetics of Cr-coated zirconium alloy: Effect of coating thickness and microstructure

Author:

Kashkarov E.B.,Sidelev D.V.,Syrtanov M.S.,Tang C.,Steinbrück M.

Funder

Russian Science Foundation

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference41 articles.

1. Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings;Tang;Corros. Rev.,2017

2. Current status of materials development of nuclear fuel cladding tubes for light water reactors;Duan;Nucl. Energy Des.,2017

3. Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings;Wagih;Ann. Nucl. Energy,2018

4. On-going studies at CEA on chromium coated zirconium based nuclear fuel claddings for enhanced accident tolerant LWRs fuel;Brachet;Proc. 2015 LWR Fuel Perform/TopFuel,2015

5. Accident tolerant fuel cladding development: promise, status, and challenges;Terrani;J. Nucl. Mater.,2018

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