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Meeting Materials Science & Technology 2019
Symposium Materials Issues in Nuclear Waste Management
Organizer(s) Jake W. Amoroso, Savannah River National Laboratory
Kyle S. Brinkman, Clemson University
Kevin M. Fox, Savannah River National Laboratory
Cory L. Trivelpiece, Savannah River National Laboratory
Jarrod Crum, Pacific Northwest National Laboratory
Scope More than half a century has been spent developing nuclear infrastructure for defense, energy, and other applications throughout the world. The scale of these activities has, and will continue to result in a significant quantity of radioactive waste. Responsible environmental stewardship requires treatment and stabilization of these radioactive wastes. This symposium will address contemporary immobilization technologies as well as challenges to develop waste forms and treatment strategies for the future. Progress and prospects in glass and cementitious waste forms as well as treatment and capture of secondary waste streams including process off-gas and liquid effluent will be discussed. Additionally, the symposium will focus on recent advances made in characterization techniques, synthesis methods, and modeling strategies of waste form development including progress made towards assessing and predicting the durability of waste forms on geological timescales. Papers are solicited on a wide variety of topics related to materials aspects in nuclear waste management using experiment, theory, and simulation. This symposium is endorsed by the ACerS Nuclear and Environmental Technology Division.
Abstracts Due 04/05/2019
Proceedings Plan Definite: At-meeting proceedings

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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