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Meeting Materials Science & Technology 2019
Symposium Materials Issues in Nuclear Waste Management
Presentation Title Dechlorination Methods and Ceramic Waste Forms for the Immobilization of Electrorefiner Salt
Author(s) Levi Gardner
On-Site Speaker (Planned) Levi Gardner
Abstract Scope Glass-bonded sodalite is currently the most promising ceramic waste form for the disposal of electrorefiner waste salt from pyroprocessing. Despite its excellent chemical durability, this waste form’s effectiveness is hindered by limited fission product loading. This report provides an overview of alternative processes with higher fission product loadings in final waste forms. Two main processing paths are discussed. The first path involves the dechlorination of waste salt via ion exchange with H-Y zeolite and consolidation through sintering. The second path involves the use of boric acid and silicic acid as dechlorinating agents and consolidation through melting or sintering. Physical properties including chemical durability and final storage volume are compared among these processes.

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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