ProgramMaster Logo
Conference Tools for Materials Science & Technology 2019
Register as a New User
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools
About this Abstract
Meeting Materials Science & Technology 2019
Symposium Materials Issues in Nuclear Waste Management
Presentation Title Energetics and Structure of Uranium-incorporated Iron Oxides
Author(s) Andy Lam, Katherine Morris, Samuel Shaw, Jesús M Velázquez, Alexandra Navrotsky
On-Site Speaker (Planned) Andy Lam
Abstract Scope Iron oxides are ubiquitous in nature and may be found as corrosion products in geological waste repositories. Their ability to structurally incorporate uranium, rather than only surface adsorb, is a promising immobilization pathway for remediating contaminated waters. However, it is not yet clear how stability scales with incorporation capacity. Iron oxide polymorphs have been synthesized with high levels of uranium incorporation and phase purity, e.g. 5 wt % U in hematite. Such samples facilitate studying thermodynamic costs of uranium loading through oxide melt solution calorimetry. Determining their formation enthalpies relative to mixtures of iron and uranium oxides may constrain stability of uranium retention over geologic timescales. X-ray absorption spectroscopy has been performed to explore local U coordination for varying degrees of incorporation. These complementary techniques provide insight to the stability and effectiveness of iron oxides for radionuclide immobilization.


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

Questions about ProgramMaster? Contact