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Meeting MS&T25: Materials Science & Technology
Symposium Ceramic Materials for Nuclear Energy System
Presentation Title Analysis of Crucible-Scale Corrosion Testing of Monofrax® K-3 Refractory in Contact with Glass Melts
Author(s) Matthew Page, Jake Amoroso, Nicodemus Rod, Daniel Odell
On-Site Speaker (Planned) Matthew Page
Abstract Scope Refractory ceramic block has been used as the liner material in glass vitrification furnaces for years. Nuclear waste glass melter liners are generally designed based on corrosion estimates obtained from crucible-scale laboratory testing. However, these estimates are known to be conservative in comparison to the service life of existent nuclear waste glass melters. Nonetheless, the results of these corrosion tests help with the understanding of the mechanisms that are predominately affecting the corrosion rate and as such can be used to refine predictions of the melter liner service life. We will present testing results aimed to support ongoing efforts to understand refractory corrosion across an expanded glass composition region. The results will be used to facilitate predictive modeling of melter liner service life, which directly influences the long-term cost of nuclear waste vitrification.

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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