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Meeting Materials Science & Technology 2019
Symposium Materials Issues in Nuclear Waste Management
Presentation Title Disorder and Mass Transport in Model Waste Forms
Author(s) Blas P. Uberuaga
On-Site Speaker (Planned) Blas P. Uberuaga
Abstract Scope One factor in the expansion of nuclear energy is the handling of nuclear waste. Many studies have examined the stability of model nuclear waste forms, such as pyrochlores, under irradiation scenarios, focused on aspects such as disordering and amorphization transformations. However, less attention has been given to the kinetics that govern the evolution of radiation-induced damage. In this work, we have examined the kinetics in these materials through a combination of modeling, particularly accelerated molecular dynamics, and experiment, using AC impedance spectroscopy to examine transport in irradiated pyrochlore. We find a strong relationship between the cation state in the material and the transport of species. Further, there is a dynamic relationship between these, with disorder inducing cation migration which further induces reordering of the structure. These results provide new insight into the long-term evolution of these materials.


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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