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 P3-70: Glass Pool Flow in a Joule-Heated, Laboratory-Scale Melter
Author(s) Derek Cutforth, Derek Dixon, Jesse Lang, Will Eaton, Mike Schweiger
On-Site Speaker (Planned) Derek Cutforth
Abstract Scope The Hanford Tank Waste Treatment and Immobilization Plant is being constructed to vitrify on-site nuclear waste. To convert the waste to glass, slurry feed (a mix of liquid waste and glass forming additives) is charged into a joule-heated melter operating at 1150C. As the feed heats up, glass-forming reactions occur, and this reacting layer is referred to as the cold cap. To create cold-cap samples in the laboratory, a 10-cm fused-silica melter vessel was loaded with glass and heated by an external furnace while continuously charging slurry feed for a fixed amount of time. To better simulate conditions in the glass melters, the vessel was redesigned for the placement of electrodes in the glass melt so the system could be joule-heated. The convective flow in the glass melt was observed and is discussed with and without joule-heating as well as with and without the presence of a cold cap.

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