Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant: Microstructure and stress corrosion cracking

22Citations
Citations of this article
12Readers
Mendeley users who have this article in their library.
Get full text

Abstract

Alloy 690TT tube samples with different scratch depths were repaired by grinding treatments using abrasive papers of two different particle sizes. The microstructure and stress corrosion cracking (SCC) behavior were studied in detail. During grinding, the plastic accumulation zone vulnerable to SCC was removed. Meanwhile, some residual slip steps remained in the scratched area. Corrosion tests lasting 1000, 2000, 3000, and 4000 h show that the sensitivity and risk of SCC in the scratched area are decreased by grinding. Treatment using abrasive particles of a smaller size is more effective. Nevertheless, deep scratches remained hazardous even after the grinding.

Cite

CITATION STYLE

APA

Wu, B., Ming, H., Meng, F., Li, Y., He, G., Wang, J., & Han, E. H. (2022). Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant: Microstructure and stress corrosion cracking. Journal of Materials Science and Technology, 113, 229–245. https://doi.org/10.1016/j.jmst.2021.11.009

Register to see more suggestions

Mendeley helps you to discover research relevant for your work.

Already have an account?

Save time finding and organizing research with Mendeley

Sign up for free