Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
9952574 | Wear | 2018 | 8 Pages |
Abstract
Fretting wear caused by flow-induced structural vibrations is a concern in the nuclear industry. The wear behavior of alloy 690 steam generator (SG) tube fretting against AISI 405 stainless steel, and exposed to 285â¯Â°C water and argon, was investigated using a fabricated apparatus. Compared with argon, high temperature water contributes to the removal of wear particles and the formation of oxide scale on the wear scar. Fretting promotes tribo-corrosion of alloy 690 in high temperature water and that results in the formation of a stable oxide scale. That oxide scale on the wear scar reduces the wear coefficient of the material and progressively changes the wear mode from one of delamination to one dominated by abrasion.
Related Topics
Physical Sciences and Engineering
Chemical Engineering
Colloid and Surface Chemistry
Authors
Xianglong Guo, Ping Lai, Lichen Tang, Kai Chen, Lefu Zhang,