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Meeting Materials Science & Technology 2019
Symposium Materials Issues in Nuclear Waste Management
Presentation Title Electrical Properties of Nuclear Glasses
Author(s) Muriel Neyret, Dylan Jouglard, Norma Pereira Machado, Rafael Bianchini Nuernberg, Leire del Campo, Mohammed Malki, Andrea Piarristeguy, Annie Pradel
On-Site Speaker (Planned) Rafael Bianchini Nuernberg
Abstract Scope Borosilicate glass is recognized as a reference conditioning material for High-Level radioactive Waste. In ceramic or cold crucible melters, glass melting is based on Joule effect ; molten glass electrical conductivity is then an important property to control.This study deals with the description of electric charge motion phenomena involving electrical properties of nuclear borosilicate glasses. Simplified glasses containing 5 oxides (SiO2-B2O3-Na2O-CaO -RuO2 or -MoO3), representative of HLW glasses, have been characterized in a wide range of temperature by impedance spectroscopy. The impact of heterogeneities, such as undissolved RuO2 or other crystals (CaMoO4,…) on glass electrical properties has been discussed. Whereas glass electrical conductivity is not strongly impacted by molybdate crystals, it increases suddenly when RuO2 content reaches a concentration of 2.2wt% corresponding to a low electrical percolation threshold. Electric force microscopy and some specific experiments allowed to explain this phenomenon by the enrichment of the borosilicate matrix in dissolved RuO2.


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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