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Meeting MS&T22: Materials Science & Technology
Symposium Ceramics for a New Generation of Nuclear Energy Systems and Applications
Presentation Title Synthesis and Characterization of Super Occluded LiCl-KCl in Zeolite-4A as a Chloride Salt Waste Form Intermediate
Author(s) Allison Mae Harward, Krista Carlson, Tae-Sic Yoo, Guy Frederickson, Mike Patterson, Michael Simpson
On-Site Speaker (Planned) Allison Mae Harward
Abstract Scope Electrorefiners are currently operating at Idaho National Laboratory, processing irradiated driver and blanket assemblies from Experimental Breeder Reactor-II in a molten salt consisting of eutectic LiCl-KCl with NaCl, UCl3, PuCl3, and numerous fission product chlorides. Methods are being investigated to condition this salt for interim storage. If untreated, the salt is deliquescent, so a means of mitigating moisture uptake and corrosion of metallic canisters may be needed. Results of experiments in which LiCl-KCl was occluded zeolite-4A up to 75 wt% will be presented. The zeolite is very effective at reducing uptake of water and minimizing potential corrosion of canisters in a controlled, humid environment because the free, unoccluded salt is primarily NaCl, which forms from the Na+ ions present in the zeolite framework ion exchanging with occluded LiCl-KCl.

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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