Mechanism of dislocation channel-induced irradiation assisted stress corrosion crack initiation in austenitic stainless steel-Reference-Cited by-同舟云学术

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Mechanism of dislocation channel-induced irradiation assisted stress corrosion crack initiation in austenitic stainless steel

Published:2015-10 Issue:5 Volume:19 Page:305-314
ISSN:1359-0286
Container-title:Current Opinion in Solid State and Materials Science
language:en
Short-container-title:Current Opinion in Solid State and Materials Science

Author:

McMurtrey M.D.,Cui B.,Robertson I.,Farkas D.,Was G.S.

Funder

U.S. Department of Energy

National Science Foundation

Basic Energy Sciences

Division of Materials Sciences and Engineering

Argonne National Laboratory

Publisher

Elsevier BV

Subject

General Materials Science

Reference37 articles.

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

2. Current understanding of radiation-induced degradation in light water reactor structural materials;Fukuya;J Nucl Sci Technol,2013

3. Review article. A review of irradiation assisted stress corrosion cracking;Scott;J Nucl Mater,1994

4. Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels;Busby;J Nucl Mater,2002

5. Role of radiation-induced grain boundary segregation in irradiation assisted stress corrosion cracking;Fukuya;J Nucl Sci Technol,2004

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1. Effects of precipitation on the stress corrosion crack initiation of alloy 718 in simulated pressurized water reactor primary environment;Acta Materialia;2024-09

2. Stress-Corrosion-Cracking Sensitivity of the Sub-Zones in X80 Steel Welded Joints at Different Potentials;Materials;2024-07-14

3. Effect of the triangular prism dent on stress corrosion cracking behavior of alloy 690TT heat transfer tube in a lead-containing alkaline solution;Journal of Nuclear Materials;2024-06

4. Dislocation channel broadening–A new mechanism to improve irradiation-assisted stress corrosion cracking resistance of additively manufactured 316 L stainless steel;Acta Materialia;2024-03

5. Decoupling the roles of grain boundary oxidation and stress in IASCC of neutron-irradiated 304L stainless steel;Journal of Nuclear Materials;2023-11

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