|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
||Chemical Interaction and Compatibility of Uranium Nitride and Alumina Forming Austenitic Alloys
||Andre Broussard, Dong Zhao, Jie Lian, Bruce Pint, Jiheon Jun, Jason Harp, Erofili Kardoulaki
|On-Site Speaker (Planned)
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.
||Nuclear Materials, Other, Other