A study of the zirconium alloy protection by Cr3C2–NiCr coating for nuclear reactor application

Author:

Jin Dongliang,Yang Fan,Zou Zhonghua,Gu Lijian,Zhao XiaofengORCID,Guo Fangwei,Xiao Ping

Funder

Shanghai Institutions of Higher Learning

Publisher

Elsevier BV

Subject

Materials Chemistry,Surfaces, Coatings and Films,Surfaces and Interfaces,Condensed Matter Physics,General Chemistry

Reference42 articles.

1. Zirconium alloys in nuclear technology;Krishnan;Proc. Indian Acad. Sci. (Eng. Sci.),1981

2. The effect of Zircaloy-4 substrate surface condition on the adhesion strength and corrosion of SiC coatings;Al-Olayyan;J. Nucl. Mater.,2005

3. Oxidation kinetics of Zircaloy-4 and Zr–1Nb–1Sn–0.1Fe at temperatures of 700–1200°C;Baek;J. Nucl. Mater.,2004

4. Waterside corrosion of zirconium alloys in nuclear power plants,1998

5. The Development of Zircaloys, The Development of Zircaloys, ASTM STP368-EB;Kass,1964

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