Abstract

It is very important to evaluate the fretting wear damage of heat exchanger tube in steam generator. In this study, the self-designed high-temperature fretting wear experimental equipment was used to conduct experimental studies on 316 stainless steel, commonly used as steam generator tube in nuclear power plants, at 95 °C for 24h, 48h, 72h and 120h, respectively. The effect of TBL on fretting wear behavior was analyzed. The results show that due to the formation of the third body layer, fretting wear damage does not increase significantly before 72 h. With the accumulation of damage, the third body layer was worn out and the damage continued to increase. The influence of the third body layer on the fretting wear behavior cannot be ignored.

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