Insight into the acceleration in oxidation kinetics ahead of stress corrosion crack of alloy 690 in simulated PWR primary water-Reference-Cited by-同舟云学术

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Insight into the acceleration in oxidation kinetics ahead of stress corrosion crack of alloy 690 in simulated PWR primary water

Published:2020-11 Issue: Volume:176 Page:108943
ISSN:0010-938X
Container-title:Corrosion Science
language:en
Short-container-title:Corrosion Science

Author:

Kuang Wenjun,Song Miao,Feng Xingyu

Funder

National Natural Science Foundation of China

Research Funds for the Central Universities

Xi’an Jiaotong University

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference61 articles.

1. Corrosion in Pressurized Water Reactor;Scott,2006

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

3. Historical views on stress corrosion cracking of nickel-based alloys: The Coriou effect;Staehle,2016

4. Some possible mechanisms of intergranular stress corrosion cracking of alloy 600 in PWR primary water;Scott,1993

5. Internal oxidation and embrittlement of alloy 600;Newman,1999

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1. A new sight on the fracture behavior of GH4169 produced by NaCl-induced corrosion in a humid environment of 600 °C;Corrosion Science;2024-10

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

3. Nano-micrometer scale characterization of PWSCC crack tips in the transition zone of 52M overlay and the implication to intergranular cracking;Journal of Nuclear Materials;2024-09

4. Effect of fretting wear regimes on stress corrosion cracking of Alloy 690TT in high-temperature pressurized water;Corrosion Science;2024-08

5. 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

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