| About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Presentation Title |
Understanding Tritium Permeation in FeCrAl Alloys |
| Author(s) |
Andrew K. Hoffman, Kan Sakamoto, Yogen Garud, Xunxiang Hu, Fabiola Cappia, Raul Rebak, Rajnikant V. Umretiya |
| On-Site Speaker (Planned) |
Rajnikant V. Umretiya |
| Abstract Scope |
FeCrAl alloys are an excellent candidate for accident tolerant nuclear fuel cladding due to their corrosion resistance and good mechanical properties. One potential topic for concern recently has been the hydrogen (and in particular tritium) permeation behavior of these alloys. Because ferritic alloys have the potential for having higher hydrogen permeation the current commercial Zr based alloys, tritium generated in the fuel could be released into the coolant water. This presentation will give an overview of the current work being done to understand permeation behavior in ferritic FeCrAl alloys. Attention will be given to the oxide layers which can be generated from the fuel-cladding interface and the coolant cladding interface. Such oxide layers are presumed to significantly decrease the hydrogen permeation in FeCrAl alloys. |
| Proceedings Inclusion? |
Undecided |