The initial oxidation of Zircaloy-4 in lithiated water under autoclave conditions as examined by TEM-Reference-Cited by-同舟云学术

The initial oxidation of Zircaloy-4 in lithiated water under autoclave conditions as examined by TEM

Published:2016-04 Issue: Volume:105 Page:141-148
ISSN:0010-938X
Container-title:Corrosion Science
language:en
Short-container-title:Corrosion Science

Author:

Wang Zhen,Zhou Bangxin^ORCID,Wang Boyang,Yao Meiyi,Li Qiang,Huang Jiao

Funder

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference38 articles.

1. C. Lemaignan, A.T. Motta, Zirconium alloys in nuclear applications, in Materials Science and Technology, A Comprehensive Treatment in:B.R.T. Frost (Ed.) New York, 10, 1994, 1–51.

2. Dynamical diffusion model to simulate the oxide crystallization and grain growth during oxidation of zirconium at 573 and 623 K;Garcia;J. Nucl. Mater.,1995

3. The effect of water chemistry on the corrosion behavior of zirconium alloys;Zhou;Necl. Power Eng.,2000

4. Corrosion of zirconium-base alloys —an overview;Hillner,1977

5. The breakaway oxidation of zirconium and its alloys a review;Ahmed;J. Less-Common. Metals,1975

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