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Meeting MS&T22: Materials Science & Technology
Symposium Ceramics for a New Generation of Nuclear Energy Systems and Applications
Presentation Title Sulfur Retention of Low Activity Waste Glasses
Author(s) Austin D. Stanfield, Jake W. Amoroso
On-Site Speaker (Planned) Austin D. Stanfield
Abstract Scope As a consequence of the high corrosivity of sulfate salts, models have been developed to mitigate sulfate segregation in Hanford Tank Waste Treatment and Immobilization Plant (WTP) melters, which rely on experimental data inputs. However, a disparity exists between the thermodynamic solubility limit in crucible-scale testing and the measured retained sulfur content in large scale test melters, with larger retention values corresponding to larger scale testing. A laboratory scale melter system was created to measure sulfur retention in simulated Hanford low-activity waste glass. The melter system is designed to simulate processing conditions, and was operated with simulants with matched physicochemical properties to melter feed, as opposed to reagent chemicals. This was undertaken to determine sulfur retention and elucidate the nature of the differences between crucible and melter testing. The resulting outcome should facilitate more applicable comparisons to be made between crucible melts and pilot-scale melts with the varied feed stocks.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

A Physics-Based Cluster Dynamics Model of Radiation-Enhanced Growth of Oxides
Additive Manufacturing of Ceramics for Nuclear Applications
Bismuth Loaded Carbon Foam as an Effective Radio Iodine Sorbent
Characterization of Radiation Effects in Ceramics with Spallation Neutron Probes
Characterizing Effects of Aging Bismuth Laden Sorbents in NOx Atmosphere for Radioiodine Capture
Cluster Dynamics Simulations of Point Defects and Fission Gas Evolution in Irradiated Ceramic Nuclear Fuels
Comparison of ZrC-TZM Mechanical and Structural Properties Before and After Extended Carbon Exposure
Corrosion of SiC in Molten Salt and Liquid Lead
Development of Novel TRU-containing Ceramics for Nuclear Waste Immobilization
Environmental Degradation of Ceramic Materials in Nuclear Energy Systems
Fabrication and Properties of Sintered Yttrium Hydride
Integration of Nuclear Fuel and Embedded Sensors within Additively Manufactured SiC Components
J-1: Development and Characterization of Ga/Ta Doped Li7La3Zr2O12 for Direct LiT Electrolysis
J-2: Evaluation of In-Flow Mechanical Robustness of Metal-Functionalized Porous Silica Materials
Microstructural Evolution in Ceramic Nuclear Fuels and their Surrogates under Irradiation
Modeling Vibrational Modes in Raman Spectra of ThO2
Phonon Broadening in High Entropy Ceramic Carbide
Radiation Damage of Ion-irradiated High Entropy Ceramics
Radiation Effects in Single-crystal High-entropy Oxides
SiC Oxidation and Irradiation Resistance in Advanced Nuclear Reactor TRISO Fuel
Single Component Variations in Glass Ceramic Waste Forms
Sulfur Retention of Low Activity Waste Glasses
Synthesis and Characterization of Super Occluded LiCl-KCl in Zeolite-4A as a Chloride Salt Waste Form Intermediate

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