Strain controlled fatigue tests for hot-extruded tube material of Alloy 690 (Sandvik Sanicro 69) have been performed at room temperature (RT) and at elevated temperature (204°C). The influences of temperature on the cyclic deformation behaviour and the fatigue life have been investigated. The influence of temperature on the fatigue life is relatively small in the temperature range investigated. However, the fatigue behaviour at elevated temperature is quite different from that at RT. A second cyclic strain hardening was observed at 204°C. The possible mechanisms have been investigated using transmission electron microscopy. Besides dislocation mechanism, the interactions between moving dislocations and stacking faults and between interstitial atoms and moving dislocations could also contribute to this secondary cyclic strain hardening. The formation of micro-twins during cyclic loading at 204°C and its influence on the cyclic stress-strain response were also discussed. Temperature affects both fatigue crack initiation and propagation behaviour. Increase in temperature promotes duplex slipping process, which causes the formation of striation.
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12th International Conference on Nuclear Engineering
April 25–29, 2004
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4687-3
PROCEEDINGS PAPER
Influence of Temperature on the Strain Controlled Fatigue Behaviour of Alloy 690 Tube Material
Guocai Chai,
Guocai Chai
Sandvik Materials Technology, Sandviken, Sweden
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Ping Liu,
Ping Liu
Sandvik Materials Technology, Sandviken, Sweden
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Johan Frodigh
Johan Frodigh
Sandvik Materials Technology, Sandviken, Sweden
Search for other works by this author on:
Guocai Chai
Sandvik Materials Technology, Sandviken, Sweden
Ping Liu
Sandvik Materials Technology, Sandviken, Sweden
Johan Frodigh
Sandvik Materials Technology, Sandviken, Sweden
Paper No:
ICONE12-49262, pp. 47-54; 8 pages
Published Online:
November 17, 2008
Citation
Chai, G, Liu, P, & Frodigh, J. "Influence of Temperature on the Strain Controlled Fatigue Behaviour of Alloy 690 Tube Material." Proceedings of the 12th International Conference on Nuclear Engineering. 12th International Conference on Nuclear Engineering, Volume 1. Arlington, Virginia, USA. April 25–29, 2004. pp. 47-54. ASME. https://doi.org/10.1115/ICONE12-49262
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