Effect of Thermal Aging on the Corrosion Fatigue Crack Growth of Z3CN20-09M Stainless Steels in Simulated Pressurized Water Reactor Primary Water
Year: 2026
Type: article
Source: CORROSION
DOI: 10.5006/4905
Authors: Ting Xiao, Jun Xiao, Yu Qi Zheng, Qi Xu, Shao Yu Qiu
Institution: Nuclear Power Institute of China
Language: English
Subfield: Metals and Alloys
Field: Materials Science
Domain: Physical Sciences
Open Access status: closed
OpenAlex ID: W7147295132