ProgramMaster Logo
Conference Tools for Materials Science & Technology 2019
Login
Register as a New User
Help
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 Observations of Crystal Settling Behavior in a Full-Scale HLW Melter Mock-Up
Author(s) Kevin M. Fox, Mark Fowley, Albert Kruger
On-Site Speaker (Planned) Kevin M. Fox
Abstract Scope The US Department of Energy is transitioning toward operation of the Hanford Waste Treatment and Immobilization Plant to safely dispose of defense high-level nuclear waste in borosilicate glass. For a significant fraction of these wastes, their loading in glass is limited by the formation of spinel crystals in the melt. Methods of controlling this crystallization will allow for maximizing waste loadings while protecting melter operation. Methods for recovering from unexpected accumulations of crystals must also be available to ensure longevity of the melters. A full-scale, room temperature test system is being used for direct observation of particle settling and resuspension under prototypic pouring conditions. Time-lapse photography has allowed for the determination of particle flow behavior under varying conditions, providing a basis for modeling and correlation to experimental glass melts. Recovery from significant accumulations of particles has been demonstrated, and will be linked to operating conditions via further scaled melter testing.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

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 programming@programmaster.org