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Meeting Materials Science & Technology 2019
Symposium Materials Issues in Nuclear Waste Management
Presentation Title Predicting the Density of High-Level Waste Glass Compositions
Author(s) Cory L. Trivelpiece, Thomas B. Edwards
On-Site Speaker (Planned) Cory L. Trivelpiece
Abstract Scope A model for predicting the density of high-level waste glass has been applied to a database consisting of 340 HLW glass compositions and approximately 700 other glass compositions. The model calculates the specific volume of a glass (at room temperature) as an additive property of the partial molar volumes of the glass’s oxide components. Utilizing the bound molar volume as opposed to the free molar volume of the major glass forming component oxides, the model accurately predicts the specific volume within the bounds of analytical error – that is, a regression of the predicted versus measured density yields a fit with unity slope and zero intercept and an adjusted R2 ≈ 0.95. This presentation will outline the model development and model implementation at the Defense Waste Processing Facility at the Savannah River Site.


Aerogels with Enhanced Gas Permeability and Mechanical Strength for use as Membranes in Radioiodine Capture
Dechlorination Methods and Ceramic Waste Forms for the Immobilization of Electrorefiner Salt
Disorder and Mass Transport in Model Waste Forms
Effect of Solution Chemistry on the Release Mechanism of Iodine from Iodoapatite Waste Form in Aqueous Environments
Electrical Properties of Nuclear Glasses
Energetics and Structure of Uranium-incorporated Iron Oxides
Impact of Redox on Crystallization Behavior of Spinel Crystals in HLW Borosilicate Glasses
Investigations into Physical and Chemical Characteristics of Nuclear Waste Glass Alteration Layers
Melt-Cast Ceramic Waste Forms: Laboratory Development and Scaled Demonstrations
Modeling of Carbonation Effects in a Cementitious Waste Form under Dry Environmental Conditions
Observations of Crystal Settling Behavior in a Full-Scale HLW Melter Mock-Up
Optimization of Frit Composition for Coupled Operation of the Defense Waste Processing Facility and Salt Waste Processing Facility at the Savannah River Site
P3-69: Corrosion Test Method Evaluation for Iodine Waste Forms
P3-70: Glass Pool Flow in a Joule-Heated, Laboratory-Scale Melter
P3-71: Multi-scale Structural Response of Pyrochlore Oxides to Swift Heavy Ion Irradiation
Predicting the Density of High-Level Waste Glass Compositions
The Influence of Reducing Conditions on the Stabilization of Iodine Containing Solid Secondary Wastes
The Relationship between Zeolite Type and Glass Dissolution Rate Resumption
Thermodynamics of Zeolite Precipitation in Stage III Glass Corrosion

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