Fretting wear of alloy 690 tube mated with different materials in high temperature water

Fretting wear of alloy 690 steam generator heat exchange tube against different anti-vibration bar materials is studied in simulated secondary water conditions of pressurized water reactors (PWR). The results indicate that the wear mode of alloy 690 is largely dependent on the mating materials, and the material transfer during wear influences the corrosion resistance of alloy 690. The depth and volume of the wear scar on alloy 690 is the lowest when the mating material is as-received and heat-treated 405 stainless steel, respectively. When the mating material contains higher chromium content, the wear resistance of alloy 690 tube is increased due to the chromium transferred from the mating material to alloy 690 in the fretting process.