ProgramMaster Logo
Conference Tools for Materials Science & Technology 2012
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Propose A Proceedings
Presenter/Author Tools
Organizer/Editor Tools
About this Abstract
Meeting Materials Science & Technology 2012
Symposium Materials Issues in Nuclear Waste Management in the 21st Century
Presentation Title Migration of Iodine Solidified in Ettringite into Compacted Bentonite
Author(s) Kazuya Idemitsu, Yoshihiko Matsuki, Masanao Kishimoto, Yaohiro Inagaki, Tatsumi Arima, Yoshiko Haruguchi, Yu Yamashita, Michitaka Sasoh
On-Site Speaker (Planned) Kazuya Idemitsu
Abstract Scope Radioactive iodine, I-129, bearing materials are produced from nuclear reprocessing plants. Cement is one of the materials for solidification of radioactive iodine. Here iodine is fixed in ettringite mineral as iodate ion. Radioactive wastes include a certain quantity of I-129 should be disposed in deep underground because the half-life of I-129 is 16 million years. When the wastes disposed, compacted bentonite would be used as a buffer material as well as for high-level radioactive waste disposal. It is concerned that radioactive iodine will be leaked from disposed waste through compacted bentonite for prolonged periods of time. Release behavior of iodine from ettringite was studied in the reducing condition by using electro-migration method as well as diffusion experiments of iodine ion and iodate ion in compacted bentonite.
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

Questions about ProgramMaster? Contact programming@programmaster.org