Study on High-Cycle Fatigue Behavior for TA16 and 690 Tube

Zhao Yuxiang; Liu Ranchao; He Kun; Xiong Ru; Wang Li

doi:10.13832/j.jnpe.2017.05.0129

Volume 38 Issue 5

Feb. 2025

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Zhao Yuxiang, Liu Ranchao, He Kun, Xiong Ru, Wang Li. Study on High-Cycle Fatigue Behavior for TA16 and 690 Tube[J]. Nuclear Power Engineering, 2017, 38(5): 129-131. doi: 10.13832/j.jnpe.2017.05.0129

Citation:

Zhao Yuxiang, Liu Ranchao, He Kun, Xiong Ru, Wang Li. Study on High-Cycle Fatigue Behavior for TA16 and 690 Tube[J]. Nuclear Power Engineering, 2017, 38(5): 129-131. doi: 10.13832/j.jnpe.2017.05.0129

Zhao Yuxiang, Liu Ranchao, He Kun, Xiong Ru, Wang Li. Study on High-Cycle Fatigue Behavior for TA16 and 690 Tube[J]. Nuclear Power Engineering, 2017, 38(5): 129-131. doi: 10.13832/j.jnpe.2017.05.0129

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Study on High-Cycle Fatigue Behavior for TA16 and 690 Tube

doi: 10.13832/j.jnpe.2017.05.0129

Science and Technology on Reactor Fuel and Material Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2017-03-12
Rev Recd Date: 2017-07-10

Available Online: 2025-02-09

Abstract

Abstract

The high-cycle fatigue experiments for steam generator tube including TA16 and 690 were conducted under axial loadings. The environments were at room temperature in air. The S-N curves were processed according to the experimental data, and the fatigue limit of the cycle is obtained by fitting formula. The fracture morphology was observed by SEM, and the fracture morphology presents areas of crack initiation, crack growth and fracture.
- Heat transfer tube material,
- Stress-cycle,
- High cycle fatigue