4.6 Article

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

Journal

NUCLEAR ENGINEERING AND TECHNOLOGY
Volume 51, Issue 2, Pages 479-489

Publisher

KOREAN NUCLEAR SOC
DOI: 10.1016/j.net.2018.10.007

Keywords

Environmentally-assisted fatigue; Alloy 690; 316 SS; Oxide layer; Electrochemical analysis

Funding

  1. Korea Hydro and Nuclear Power Co., Ltd. as the Proactive Material Aging Management Project
  2. KUSTAR-KAIST Institute of KAIST
  3. MSIP/NRF (Engineering Research Center) of MSIP of the Republic of Korea [2016R1A5A1013919]
  4. BK-Plus Program of the MSIP of the Republic of Korea

Ask authors/readers for more resources

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. (C) 2018 Korean Nuclear Society, Published by Elsevier Korea LLC.

Authors

I am an author on this paper
Click your name to claim this paper and add it to your profile.

Reviews

Primary Rating

4.6
Not enough ratings

Secondary Ratings

Novelty
-
Significance
-
Scientific rigor
-
Rate this paper

Recommended

No Data Available
No Data Available