| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
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| Presentation Title |
Chemical Interaction and Compatibility of Uranium Nitride and Alumina Forming Austenitic Alloys |
| Author(s) |
Andre Broussard, Dong Zhao, Jie Lian, Bruce Pint, Jiheon Jun, Jason Harp, Erofili Kardoulaki |
| On-Site Speaker (Planned) |
Andre Broussard |
| Abstract Scope |
Uranium Nitride (UN) and Alumina Forming Austenitic Alloys (AFAs) have been identified as a potential fuel-cladding combination for Westinghouse’s lead cooled fast reactor (LFR). The chemical interaction between UN (monolithic and with expected secondary phases), preoxidized (alumina scaling on the surface), and as-cast (no alumina scaling) AFA, was investigated by utilizing a diffusion couple setup consisting of spark plasma sintered UN pellets and AFA coupons prepared by ORNL. The diffusion couples were isothermally annealed at both 550℃ and 750℃ for 500 and 1000 hours under inert conditions. Preoxidized AFA exhibits a significant reduction of interaction with UN compared to as-cast AFA due to the protective alumina scaling. Interaction between as-cast AFA and UN exhibits the formation of aluminum nitride and a suspected uranium-iron ternary phase. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Other, Other |