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Meeting Materials Science & Technology 2016
Symposium Materials Issues in Nuclear Waste Management in the 21st Century
Jake W. Amoroso, Savannah River National Laboratory
Isabelle Giboire, CEA Marcoule
Raghunath Kanakala, University of Idaho
Yutai Katoh, Oak Ridge National Laboratory
Stefan Neumeier, Forschungszentrum Juelich GmbH
David Shoesmith, Western University
Kumar Sridharan, Univ of Wisconsin-Madison
David Enos, Sandia National Laboratories
Charles Bryan, Sandia National Laboratories
Scope Nuclear energy offers a viable solution to the world’s increasing demand for electricity, state’s dependence on imported oil, and global air pollution and climate change. However, an increasing inventory of nuclear waste poses a significant environmental challenge. The expectations of waste form materials performance are stringent due to the need for long term stewardship of nuclear waste. Nuclear waste comprises a variety of materials requiring different types of management to protect people and the environment. New or improved technologies and materials are needed to achieve safe and hazard-free generation, processing, storage, transport, and disposal of nuclear waste. In addition, a better scientific understanding of the processes and mechanisms underlying the long-term behavior of waste forms is needed.

This symposium will discuss fundamental and applied scientific topics related to materials issues in nuclear waste management. The symposium will include a special session “The Impact of Extended Dry Storage on Used Nuclear Fuel” focused on topics aimed at understanding uncertainties (environmental conditions that are present on the surface of the storage containers and the electrochemical properties of the storage containers) associated with the interim storage of used nuclear fuel. The symposium will feature the internationally renowned speakers and leading researchers investigating novel materials and technologies using experiments, theory, mathematical and physical modeling, and simulation.
Abstracts are solicited in (but not limited to) the following topics:
• Waste forms
• Advanced waste-form technologies (e.g., vitrification, cementation, and grout)
• Waste treatment for remediation of radionuclides
• Volatile radionuclide removal and immobilization
• Sequestration of high-level nuclear waste
• Special session “The Impact of Extended Dry Storage on Used Nuclear Fuel”
• Nuclear waste management programs around the world
• Cross-cutting topics
Abstracts Due 03/31/2016
Proceedings Plan Planned: Other (journal publication, etc.; describe below)

A Model for the Corrosion of Spent Nuclear Fuel within a Failed Nuclear Waste Container
Advanced Waste Form Technologies with a Focus on Hot Isostatic Pressing
An Integrated Computational Materials Engineering (ICME) Model of Chloride Induced Stress Corrosion Cracking in Dry Canister Storage Systems of Spent Nuclear Fuel
Aqueous Synthesis of Iodide Sodalite
Cesium Immobilization in Zinc Doped Hollandite
Characterization of Radiation Effects in Complex-oxide Nuclear Waste Forms: New Application of Neutron Total Scattering Techniques
Chemical and Physical Environment on the Surface of SNF Interim Storage Canisters
Chloride-induced Stress Corrosion Cracking (CISCC) Aging Management Guidelines and Inspection Capabilities
Corrosion Behavior of 410 SS/Ceramic Composite Waste Forms
Crystal Accumulation Studies for Nuclear Waste Melters
Effect of Anions on Sulfur Solubility in Low-Activity Waste Glass
Effect of Phase Assemblage and Chemical Speciation on the Durability of Multiphase Ceramics
Effects of α-Radiation on a Disposal of Spent Nuclear Fuel
Electrochemical Corrosion Behavior of an HT9 Based Alloyed Waste Form
Electrochemical Studies of Lanthanide Chlorides in Molten Eutectic LiCl-KCl
Estimating Bounding Corrosion Pit Sizes on Stainless Steel SNF Interim Storage Canisters
Identification of Reactions during Melting of Low-activity Waste Glasses by Evolved Gas Analysis
Immobilisation of I in AgI Sodalite, Ag4Al3Si3O12I
Immobilisation Options for Exotic Carbide Fuels
Incorporation of Ba in Al and Fe Pollucite
Innovative Approaches to Marine Atmospheric Stress Corrosion Cracking Inspection, Evaluation and Modeling in Used-fuel Dry Storage Canisters
Key Data Gaps in Assessing the Chloride Induced Stress Corrosion Cracking of Interim Storage Containers for Spent Nuclear Fuel
Lead Vanadate Apatite for Immobilization of I-129
Liquid Secondary Waste: Waste Form Development
Low Temperature Waste Form Process Intensification
Microbial Impacts on Materials Containing Radioactive Waste
Modeling the Long Term Degradation of Used Nuclear Fuel Canisters
Nanoscale Investigation and Control of Radionuclides in Waste Management
Nepheline Crystallization Kinetics in Simulated High Level Waste Glasses
New Binders, New Trends, New Potentialities in Waste Cementation
Peraluminous Glassy Matrices for Fission Products and Actinides Conditioning
Performance of Tc and I Getters in Cementitious Waste Forms
Radiation Stability and Chemical Durability of Cerium Substituted Zirconolite (CaZrTi2O7) and Pyrochlore (Nd2Ti2O7)
Revised Models for the Defense Waste Processing Facility (DWPF)
Rhenium Partitioning in Simplified Low-activity Waste Glass Feed
Role of Platinum Group Metals on Rheological and Electrical Properties of Nuclear Glass
SCC Detection and Life Predication for Nuclear Waste Management Using PGAA and NAA
Silver-functionalized Silica Aerogel for Highly Efficient Capture and Sequestration of Iodine from Low-activity Waste Off-gas Condensate
Structural Characterization and Cesium Retention of (Ba,Cr)-hollandites
The Effect of Composition on the Local Structure of Alkali Alumino Borosilicate Model Glasses for Comparison with Hanford High-level Waste Glasses
Understanding the Risk of Chloride Induced Stress Corrosion Cracking of Interim Storage Containers for the Dry Storage of Spent Nuclear Fuel: Residual Stresses in Typical Welded Containers
Use of X-Ray Tomography to Elucidate Cold Cap Structure in Waste Glass Melter
Volatilization of Alkali Perrhenates from Sulfate and Nitrate Salt Mixtures
Volumetric Stabilization of Ceramic Waste Forms
Waste Forms for the Immobilization of Highly Enriched Uranium Waste Streams from Mo-99 Production
XTractite: An Inorganic Ion-exchange Material for Sorption of Radionuclides

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