|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
||Nuclear fuels and interfaces for advanced specialty microreactors
||Erofili Kardoulaki, Najeb Abdul-Jabbar, Josh White, Scarlett Widgeon-Paisner, Maria Kosmidou, Mehadi Hassan, Ken McClellan
|On-Site Speaker (Planned)
Multiple agencies are investing heavily in specialty microreactor technologies to support terrestrial power applications where grid support is limited and extraterrestrial applications supporting manned missions for deep space exploration. Microreactors present unique design and materials challenges and must be commercially attractive in order to succeed. In all cases fuels that enable high thermal conductivity throughout the reactor lifetime and can withstand exposure to extreme environments (e.g. H2 and graphite exposure) are key. In many cases carburization is a key consideration, due to the graphite core that is used to provide increased moderation, and protective coatings have to be employed to ensure safe and robust operation. Fuel-cladding systems in contact with graphite, i.e. UN-Zr-C, will be discussed in the context of materials performance optimization to provide robust systems that will retain fission products during normal and off-normal operation, promote heat transfer, and ensure mechanical integrity.
||Nuclear Materials, Characterization, High-Temperature Materials