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Meeting MS&T25: Materials Science & Technology
Symposium Ceramic Materials for Nuclear Energy System
Presentation Title Stabilization of Research Reactor Spent Nuclear Fuel to Ceramic Form for Potential Disposal in a Deep Geological Repository
Author(s) Anil Prasad, Aaron Barry, Ernesto Geiger, James Crigger, Madalena Spencer, Ray Dickson
On-Site Speaker (Planned) Anil Prasad
Abstract Scope Research Reactor Spent Nuclear Fuel (RRSNF) in Canada includes non-oxide forms such as uranium metal, uranium alloys and compounds. These materials are reactive in groundwater and are likely unsuitable for direct disposal in a Deep Geological Repository (DGR), unlike CANDU fuel, which is a relatively stable ceramic uranium dioxide. Hence, RRSNF may need to be converted into durable, oxide-based waste forms for acceptance into a DGR. At Canadian Nuclear Laboratories, ongoing research focuses on oxidation followed by Spark Plasma Sintering (SPS) to densify converted materials into corrosion-resistant ceramics. SPS enables rapid consolidation at relatively low temperatures, producing dense pellets with improved DGR characteristics compared to their original form. This work outlines a path to stabilizing RRSNF for long-term containment, supporting Canada’s strategy for the safe disposal of all spent nuclear fuel types. The SPS-processed materials demonstrate the potential to achieve characteristics equivalent to CANDU fuel within a multi-barrier repository system.

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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