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Meeting MS&T25: Materials Science & Technology
Symposium Ceramic Materials for Nuclear Energy System
Presentation Title Chemical Durability of Cermet Waste Forms for Advanced Reactor Wastes
Author(s) Jake W. Amoroso, Matthew Page, Nathaniel Marrero, Shanmugavelayutham. K. Sundaram, Alevtina Maksimova, Gregory Morrison, Hans-Conrad zur Loye
On-Site Speaker (Planned) Jake W. Amoroso
Abstract Scope The next generation of Advanced Reactors (ARs) for nuclear energy production are currently being developed in the United States. Integral to commercialization of AR systems are novel waste form solutions that maintain the requisite performance characteristics and safeguard standards as well as the accepted back-end costs in the range of $1/megawatt-hour. Development is underway to demonstrate a simple, rapid, and scalable process capable of immobilizing multiple waste streams from multiple fuel cycles into a durable cermet waste form. The proposed cermet would comprise a metal matrix (e.g., stainless steel) encapsulating dispersed durable ceramic phases derived from constituent salt (halides); oxide; and carbide/C-14 wastes. Correlation of the measured performance with the phase assemblage and chemistry is needed to design and, ultimately, demonstrate the viability of potential cermet waste forms. The results of chemical durability testing on ceramic phases, alloy phases, and consolidated cermet materials is presented.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Analysis of Crucible-Scale Corrosion Testing of Monofrax® K-3 Refractory in Contact with Glass Melts
Chemical Durability of Cermet Waste Forms for Advanced Reactor Wastes
Cluster Dynamics Modeling of Extended Defect Evolution with Loop Unfaulting in Proton-Irradiated Single Crystal ThO2
Dechlorination and Immobilization of Electrorefiner Salt Waste in Phosphate Glass Matrices
In Situ High-Temperature Behavior of Uranium Borides
Point Defect Energetics in AlGaN Alloys by Machine Learning Force Field
Stabilization of Research Reactor Spent Nuclear Fuel to Ceramic Form for Potential Disposal in a Deep Geological Repository
Swift Heavy Ions to Study Amorphization Behavior of Compositionally Complex Oxides
Synthesis and Characterization of Rhenium Chalcogenides for Nuclear Waste Management
The Role of Microstructures in Hydrogen Retention in Zirconium Hydride Moderator

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