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Meeting MS&T24: Materials Science & Technology
Symposium Progressive Solutions to Improve the Corrosion Resistance of Nuclear Waste Storage Materials
Presentation Title Structural Design of Borosilicate-Based Nuclear Waste Glasses
Author(s) Ashutosh Goel
On-Site Speaker (Planned) Ashutosh Goel
Abstract Scope Borosilicate glasses are vital for immobilizing nuclear waste due to their unique processing and product traits. Traditionally, designing these glasses relied on trial-and-error, followed by empirical models for prediction. Yet, this method has drawbacks: it limits enhanced waste loadings and struggles to explain deviations from predictions. Transitioning beyond the trial-and-error approach is crucial, requiring a fundamental understanding of compositional and structural descriptors governing the processing, properties, and performance of the borosilicate-based nuclear waste glasses. This presentation explores structural design strategies, focusing on suppressing aluminosilicate crystallization and increasing sulfur solubility in the glassy matrix. This shift is essential for advancing nuclear waste glass design beyond empirical models, enabling greater efficiency and predictability in waste immobilization.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Neutron Diffraction Residual Stress Characterization of Stainless Steel Produced by Wire Arc Direct Energy Deposition
Polymer-Derived Ceramic Coatings for Nuclear Waste Storage Canister Corrosion Prevention
Quantitative Analysis of Hydrogen Interactions with UO2 Grain Boundaries Using Density Functional Theory
Structural Design of Borosilicate-Based Nuclear Waste Glasses
Structural Origin of the Passivation Effect Nuclear Waste Immobilization Glasses
Transition Metal Ions Induced Structural Rearrangements and Their Impact on Sulfur Solubility in Borosilicate-Based Model Nuclear Waste Glasses

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