Effect of irradiation on corrosion of 304 nuclear grade stainless steel in simulated PWR primary water-Reference-Cited by-同舟云学术

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Effect of irradiation on corrosion of 304 nuclear grade stainless steel in simulated PWR primary water

Published:2017-10 Issue: Volume:127 Page:91-100
ISSN:0010-938X
Container-title:Corrosion Science
language:en
Short-container-title:Corrosion Science

Author:

Deng Ping,Peng Qunjia,Han En-Hou,Ke Wei,Sun Chen,Jiao Zhijie

Funder

International Science & Technology Cooperation Program of China

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference48 articles.

1. IASCC susceptibility and slow tensile properties of highly-irradiated 316 stainless steels;Fukuya;J. Nucl. Sci. Technol.,2004

2. Crack initiation behavior of neutron irradiated model and commercial stainless steels in high temperature water;Stephenson;J. Nucl. Mater.,2014

3. Role of slip behavior in the irradiation assisted stress corrosion cracking in austenitic steels, Proc;McMurtrey,2011

4. Localized deformation and IASCC initiation in austenitic stainless steels;Jiao;J. Nucl. Mater.,2008

5. IASCC initiation in highly irradiated stainless steels under uniaxial constant load conditions;Nishioka;J. Nucl. Sci. Technol.,2008

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