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Meeting MS&T25: Materials Science & Technology
Symposium Ceramic Materials for Nuclear Energy System
Presentation Title Synthesis and Characterization of Rhenium Chalcogenides for Nuclear Waste Management
Author(s) Logan S. Breton, Jake Amoroso
On-Site Speaker (Planned) Logan S. Breton
Abstract Scope Technetium (Tc) present in radioactive waste has a long half-life, ~200,000 years, and is environmentally mobile, which poses challenges to manage the long-term dose from exposure. TcS2 has been deemed a potential waste form material though a significant obstacle to progress is the limited synthetic pathways that exist to prepare the material. This has led us to investigate a new synthetic pathway to Tc chalcogenides utilizing the boron-chalcogen mixture (BCM) method as a facile route to synthesize technetium chalcogenide materials. This talk will present the current results of preliminary research on the synthesis of rhenium (Re) chalcogenides using the BCM method as well as thermal analysis and high temperature PXRD performed on the synthesized materials. Plans for the translation of this work to technetium containing systems will also be 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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