Crevice corrosion behavior of Alloy 690 in high-temperature water-Reference-Cited by-同舟云学术

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Crevice corrosion behavior of Alloy 690 in high-temperature water

Published:2019-03 Issue: Volume:515 Page:326-337
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Ning Fangqiang,Wu Xinqiang,Tan Jibo

Funder

National Natural Science Foundation of China

National Science and Technology Major Project

Key Programs of the Chinese Academy of Sciences

Innovation Fund of Institute of Metal Research

Chinese Academy of Sciences

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference49 articles.

1. Materials challenges in nuclear energy;Zinkle;Acta Mater.,2013

2. Internal oxidation of alloy 690 in hydrogenated steam;Persaud;Corros. Sci.,2015

3. Technical Note: investigation of oxide film formed on Alloy 690 (TT) tubes in alkaline water;Jiang;Corrosion,2017

4. Transport processes in steam generator crevices—I. general corrosion model;Engelhardt;Corros. Sci.,1999

5. Transport processes in steam generator crevices. II. A simplified method for estimating impurity accumulation rates;Engelhardt;Corros. Sci.,1999

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