| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Components
|
| Presentation Title |
Creep Crack Growth Behaviour of Austenitic Stainless Steels Alloy 709 and 316H |
| Author(s) |
Suyang Yu, Jin Yan, Hangyue Li, Afsaneh Rabiei, Paul Bowen |
| On-Site Speaker (Planned) |
Suyang Yu |
| Abstract Scope |
Alloy 709, a new austenitic stainless steel, is considered as the structural material for the next-generation sodium-cooled fast neutron reactor due to its superior creep resistance. Knowledge of crack growth in this new material under creep is essential to the life prediction with the consideration of the possible fracture originating from existing flaws. To address this, creep crack growth behaviour (rates and failure mechanisms) in Alloy 709 are tested using compact tension testpieces at 550 to 750°C. 316H is also tested at 650°C as a baseline. Crack growth rates are characterized using elastic-plastic C* and linear elastic stress intensity factor. Their validity and applications in creep crack growth are discussed. Consistent with their creep properties, Alloy 709 shows a much better creep crack growth resistance than 316H. Failure mechanisms in Alloy 709 are found to depend on temperature and load, and appears to be different from 316H. |
| Proceedings Inclusion? |
Planned: |