Stress corrosion cracking susceptibility of thermally-aged Type 310S stainless steels in supercritical water-Reference-Cited by-同舟云学术

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Stress corrosion cracking susceptibility of thermally-aged Type 310S stainless steels in supercritical water

Published:2018-05 Issue: Volume:135 Page:1-11
ISSN:0010-938X
Container-title:Corrosion Science
language:en
Short-container-title:Corrosion Science

Author:

Jiao Yinan,Zheng Wenyue,Kish Joseph R.

Funder

Office of Energy Research and Development

Natural Sciences and Engineering Research Council of Canada

Natural Resources Canada

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference60 articles.

1. 5.12 − Material performance in supercritical water;Allen,2012

2. Supercritical water-cooled reactor materials –summary of research and open issues;Guzonas;Prog. Nucl. Energy,2014

3. Cycle chemistry and its effect on materials in a supercritical water-cooled reactor: a synthesis of current understanding;Guzonas;Corros. Sci.,2012

4. Historical experience providing bases for predicting corrosion and stress corrosion in emerging supercritical water nuclear technology: part 1 – review;Ru;Corrosion,2013

5. Historical experience providing bases for predicting corrosion and stress corrosion in emerging supercritical water nuclear technology: part 3-review;Ru;Corrosion,2013

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5. Effect of Short-Time Aging on the Sensitization Characteristics of 310S Stainless Steel;International Journal of Electrochemical Science;2022-09

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