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Meeting Materials Science & Technology 2012
Symposium Materials Issues in Nuclear Waste Management in the 21st Century
Presentation Title Adsorption of of Radioactive Iodine from Used Nuclear Fuel Reprocessing using Granular Solid Sorbents
Author(s) Nick Soelberg
On-Site Speaker (Planned) Nick Soelberg
Abstract Scope Assessments have been made that suggest that radioactive iodine that could evolve during used nuclear fuel reprocessing may require control efficiencies greater than 99.9% to meet regulatory air emission limits in the U.S. Granular solid sorbents have been demonstrated in "deep-bed" tests to assess the performance of granular solid sorbents for capturing iodine species in off-gas streams. Sorbents that have been tested to date include selected silver-impregnated zeolites and engineered sorbents. The multi-stage test system design has provided the ability to determine (a) the sorbent capacity, b) the sorbent capture efficiency, and (c) the mass transfer zone. Test results indicate that, for expected off-gas conditions for aqueous used fuel reprocessing, efficiencies of between 99.9 - 99.99% are possible. This work has been funded by the U.S. Department of Energy Advanced Fuel Cycle Research and Development Program Separations and Waste forms Campaign.
Proceedings Inclusion? Planned:

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Adsorbents of Titanate Nanofibers and Nanotubes for the Removal of Radioactive Ions from Contaminated Water
Adsorption of of Radioactive Iodine from Used Nuclear Fuel Reprocessing using Granular Solid Sorbents
Advanced Ceramic Waste Forms for the Immobilisation of Radioactive Wastes
Advanced Electrochemical Waste Forms
Advances in JHCM HLW Vitrification Technology through Scaled Melter Testing
Burst, Ring and Biaxial Creep of Zircaloy Cladding – Applications to Dimensional Change Predictions during Dry Storage
Conditioning of Iodate Ion in an Apatite-Like Ceramic
Determining Thermal Conductivity of Simulated Feed for High Level Waste Glass
Development of Structure in Saltstone Grout Slurries
Effect of Temperature on the Crevice Corrosion Susceptibility of Passivating Nickel Based Alloys
Effect of the Ratio of B/Al on Glass Dissolution along the Nepheline (NaAlSiO4) – Malinkoite (NaBSiO4)
Electrochemical and Thermal Properties of Rare-Earth Chlorides in Molten LiCl-KCl for Nuclear Waste Separation
Environmental Cracking of Nickel Alloys in Bicarbonate and Chloride Solutions
Epsilon Metal Waste Form Development for Fission Products in Used Nuclear Fuel
High and Intermediate Level Nuclear Waste Forms
Impact of Particle Agglomeration on Accumulation Rates in the Glass Discharge Riser of HLW melter
Lead-and Boron-Based Chemically Bonded Phosphates Ceramics for Nuclear Waste Stabilization and Irradiation Shielding Applications
Migration of Iodine Solidified in Ettringite into Compacted Bentonite
Multiscale Modeling for Predicting Long-Term Behavior of Glass Wasteforms in a Nuclear Waste Repository
Radioactive Demonstrations of Fluidized Bed Steam Reforming (FBSR) with Hanford Low Activity Wastes
Radionuclide Behavior and Geochemistry in Boom Clay after Geological Disposal of High-Level Waste
Recent Advances in the Capture/Sequestration of Volatile Radionuclides from Fuel Reprocessing
REDuction/OXidation (REDOX) Modeling and Process Control in the Defense Waste Processing Facility (DWPF): Impacts of Antifoam and Ar Bubbling
Removal of Xenon and Krypton from Air Using Metal Organic Frameworks
Sodalite-Based Forms for Wastes Containing Actinides and Halides
Status of High Level Waste at the Defense Waste Processing Facility through Sludge Batch 7b
Sulfate Volatilization in Simulated Nuclear Waste Glasses
The Development of Glass Compositions for the Vitrification of Ion Exchange Resin Wastes
The Effect of Particle Geometry on the Dissolution Behavior of Glasses
The Effect of Placement Conditions and Curing Environment on the Leaching Performance of Cementitious Waste Grouts
The Effects of Lithium Nitrate on Highly Active Liquor in the Calcination Process
The Use of Ancient Glasses in Understanding the Mechanism for Glass Dissolution Disposal
The Use of Cold Crucible Induction Melters for Effectively Producing Advanced Glass -Ceramic Radioactive HLW Forms
Utilizing Oxygen Uptake to Predict Lifetimes of Elastomeric O-rings
Viscosity of Multicomponent Glasses as a Function of Temperature and Composition

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