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Meeting Materials Science & Technology 2019
Symposium Materials Issues in Nuclear Waste Management
Presentation Title P3-71: Multi-scale Structural Response of Pyrochlore Oxides to Swift Heavy Ion Irradiation
Author(s) Eric O'Quinn, Igor Gussev, William Cureton, Devon Drey, Alex Solomon, Joerg Neuefeind, Maik Lang
On-Site Speaker (Planned) Eric O'Quinn
Abstract Scope A major obstacle to the disposal of high-level nuclear waste is the fabrication of durable materials that can safely immobilize radionuclides. Materials proposed for usage as waste forms in underground repositories must demonstrate stability against self-irradiation of the incorporated actinides as well as chemical durability such that radioisotopes are not leached into the environment. Some proposed ceramic waste forms that adopt the isometric pyrochlore structure (A2B2O7) exhibit excellent radiation tolerance due to accommodation of atomic-scale disordering, yet it is not yet understood how this disordering mechanism proceeds over the sub-nanoscale. Total scattering experiments provide fundamental insight into the multi-scale structural responses of swift-heavy ion irradiated pyrochlores including crystalline-amorphous and order-disorder transformations. Ion-irradiated pyrochlores are characterized by a high degree of local order with similar atomic arrangements in disordered and amorphous cases. These results provide a framework by which pyrochlore oxides can be accurately modeled for the immobilization of nuclear wastes.


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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