| About this Abstract |
| Meeting |
2022 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
|
| Presentation Title |
Creep Performance of IronClad Accident Tolerant Fuel Cladding |
| Author(s) |
Evan J. Dolley, Wanming Zhang, Dan R. Lutz, Russ M. Fawcett, Raul B. Rebak |
| On-Site Speaker (Planned) |
Evan J. Dolley |
| Abstract Scope |
The nuclear power industry has been using zircaloy alloy clad fuel for over 60 years. Since the Fukushima accident, the US Department of Energy has been working with General Electric (GE) to develop accident tolerant fuels to make the current fleet of reactors safer to operate. GE is evaluating IronClad or FeCrAl alloy as cladding for UO2 pellets. Since FeCrAl ferritic alloys have not previously been used in light water reactors, it is important to characterize their behavior over the entire fuel cycle. GE has a test method for creep testing of IronClad tubing as a function of temperature and hoop stress. Results show that powder metallurgy IronClad tubing showed diametral creep rates at temperatures up to 800°C that are several times lower than those of cladding tubes fabricated from Zircaloy-2. Creep rates of IronClad tubing have also been shown to be dependent on material chemistry and resultant microstructural conditions. |
| Proceedings Inclusion? |
Planned: |