Comparison of oxide layers formed on the low-cycle fatigue crack surfaces of Alloy 690 and 316 SS tested in a simulated PWR environment

Low-cycle fatigue (LCF) tests were performed for Alloy 690 and 316 SS in a simulated pressurized water reactor (PWR) environment. Alloy 690 showed about twice longer LCF life than 316 SS at the test condition of 0.4% amplitude at strain rate of 0.004%/s. Observation of the oxide layers formed on the...

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Bibliographic Details
Published in:Nuclear engineering and technology 2019, 51(2), , pp.479-489
Main Authors: Chen, Junjie, Nurrochman, Andrieanto, Hong, Jong-Dae, Kim, Tae Soon, Jang, Changheui, Yi, Yongsun
Format: Article
Language:English
Subjects:
원자력공학
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Summary:Low-cycle fatigue (LCF) tests were performed for Alloy 690 and 316 SS in a simulated pressurized water reactor (PWR) environment. Alloy 690 showed about twice longer LCF life than 316 SS at the test condition of 0.4% amplitude at strain rate of 0.004%/s. Observation of the oxide layers formed on the fatigue crack surface showed that Cr and Ni rich oxide was formed for Alloy 690, while Fe and Cr rich oxide for 316 SS as an inner layer. Electrochemical analysis revealed that the oxide layers formed on the LCF crack surface of Alloy 690 had higher impedance and less defect density than those of 316 SS, which resulted in longer LCF life of Alloy 690 than 316 SS in a simulated PWR environment. Keywords: Environmentally-assisted fatigue, Alloy 690, 316 SS, Oxide layer, Electrochemical analysis
ISSN:1738-5733
2234-358X
DOI:10.1016/j.net.2018.10.007