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Meeting Materials Science & Technology 2019
Symposium Materials Issues in Nuclear Waste Management
Presentation Title The Relationship between Zeolite Type and Glass Dissolution Rate Resumption
Author(s) James Neeway, Radha Motkuri, Jarrod C. Crum, Emily Freeman, Giannis Mpourmpakis, Adam Mallette, Jeffrey D. Rimer
On-Site Speaker (Planned) James Neeway
Abstract Scope Stage III is a delayed acceleration in the glass dissolution rate that coincides with the presence of zeolitic minerals in the system. Recent advances in glass corrosion science have intentionally added, or “seeded”, the system with zeolite minerals in order to initiate Stage III behavior. These seeding tests serve to more accurately measure Stage III glass dissolution rates and overcome long induction times needed for zeolite nucleation and growth. However, one main difference between these seeded tests and “natural” Stage III observations is the zeolites observed in “natural” tests do not necessarily match the list of zeolites that cause induce Stage III behavior in seeded tests. The aim of this presentation is provide results with a set of zeolite seeds and explain why only certain zeolite types induce Stage III behavior. These results can be used to design systems that limit the impact of Stage III behavior on the long-term storage of nuclear waste glass.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

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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