Session: OAC-03-02/07-01 Monitoring, Diagnostics & Inspection and Plant Life Extension: Aging & Life Management

Paper Number: 61550

Start Time: Thursday, July 15, 2021, 05:00 PM

61550 - Effect of the Third Body Layer on Fretting Wear Behavior of 316 Stainless Steel 

Steam generator is the key equipment in pressurized water reactor (PWR) nuclear power plant, which operation safety is very important. Flow-induced vibration will lead to the impact and wear between steam generator tube (SGT) and anti-vibration bar (AVB), resulting in the thinning of the SGT wall. As the damage accumulates, it is likely to cause the SGT break. This is an important reason that affects the stable operation of steam generator. This work explored the effect of oxide layer on the fretting wear damage between SGT material 316H and AVB material 316H at 95℃ in different experiment time of 24h, 48h, 72h and 120h. The results showed that the SGT wear volume increased with the increase of experiment time, but the increase rate of wear volume was first falling then rising. In the early stage of the experiment, the oxidation degree of the SGT surface was low and the oxide film was thin, which could not protect the surface. With the increase of time, the oxide film gradually thickens, avoiding the direct contact between material bodies and reducing the increase rate of wear volume. Finally, the cracks of the oxide film continued to grow and connected with each other, leading to the large-scale peeling of the oxide film. This resulted in a significant increase in fretting wear volume. This conclusion may provide experimental evidence for service life prediction and design of steam generator tube.

Presenting Author: Shengzan Zhang Tianjin University

Authors:

Shengzan Zhang Tianjin University
Liyan Liu Tianjin University
Xu Ma Tianjin University
Wei Tan Tianjin University
Guorui Zhu Tianjin University