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Meeting Materials Science & Technology 2017
Symposium Materials Issues in Nuclear Waste Management
Sponsorship
Organizer(s) Jake Amoroso, Savannah River National Laboratory
Aladar Csontos, Nuclear Regulatory Commission
Kevin Fox, Savannah River National Laboratory
Tongan Jin, Pacific Northwest National Laboratory

Yutai Katoh, Oak Ridge National Laboratory
Bill Lee, Imperial College of London
Josef Matyas, Pacific Northwest National Laboratory
Nathan Mellot, Michigan State University
Kumar Sridharan, University of Wisconsin Madison
S.K. Sundaram, Alfred University
Scope As nuclear energy and fuel reprocessing efforts expand, there is an increasing need to generate knowledge on the processing, properties, and testing of materials used in nuclear waste management. Responsible environmental stewardship requires treatment and stabilization of radioactive wastes generated from a wide variety of sources. This symposium will address the immobilization of waste using vitreous cementitious, and composite materials, the material properties of these waste forms and their long-term performance. In addition, the capture and immobilization of radionuclides from off-gas and liquid waste streams will be of interest. High-temperature ceramic, glass, and composite materials as well as alternative low-temperature hydroceramics, geopolymers, and cementitious materials will be discussed. Additional topics include characterization techniques, test methods, and modeling strategies to assess and predict the durability of waste forms on geological time scales. Papers are solicited on a wide variety of topics related to materials aspects in nuclear waste management using experiment, theory, and simulation. This symposium is endorsed by the ACerS Nuclear and Environmental Technology Division.

Abstracts are solicited in (but not limited to) the following topics:
• Waste form materials
• Advances in and design of waste forms and treatment systems
• Advanced waste-form technologies (e.g., vitrification, cementation, and grout)
• Waste treatment for remediation of radionuclides and recycle
• Capture and immobilization of volatile radionuclides
• Sequestration of high-level nuclear waste
• Long-term performance of nuclear waste forms
• International nuclear waste management programs
• The economics of waste treatment strategies
Abstracts Due 03/31/2017
Proceedings Plan Undecided
PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE

Atomistic Computer Simulations of Nuclear Waste Materials
A Brief History of the Contributions of D.T. Rankin and the D.T. Rankin Award Winners
Advanced Characterization of Model Multiphase Ceramic Waste Forms
An Empirical Model of Thermodynamic Sulfur Solubility in Nuclear Waste Glasses
Application of Evolved Gas Analysis to Nuclear Waste Feed Melting
Applications of Ancient Roman Cementitious Systems to Long Term Nuclear Waste Performance
E-15: First Principles Study of Technetium Incorporation into Sodium Borosilicate Glasses
Effect of Foaming on Heat Flux to the Cold Cap In the High-alumina HLW Melter Feed
Effect of Reducing Agents on Rhenium Retention and Feed Reactions during Melting of Low-activity Waste Glasses
Effects of Silica Saturation on ISG Corrosion in Alkaline Solutions
Efforts to Address Species of Concern in Nuclear Waste Management
Enhanced Vitrification Processing Models for High TiO2 Containing Glasses
Enhanced Waste Glass Effort: Producing Desired Properties from a Broader Spectrum of Compositions
MD Simulations of the Bulk and Surface Structures of Nuclear Waste Glasses
Multicomponent Glass Surfaces: Composition, Structure, and Reactions
Nepheline Crystal Growth in High Level Nuclear Waste Glasses
Potential Impacts of Spinel Crystallization in High Level Nuclear Waste Glasses
Predictive Modeling of Crystal Accumulation in the HLW Glass Melters Processing Radioactive Waste
Savannah River National Laboratory Strategies for Waste Treatment Processing
Sintering Behavior of Glass Binders for the Immobilization of High-Level Waste Salt
Stabilization and Solidification of Low Activity Waste and Secondary Wastes Arising from Treatment of Nuclear Fuel Reprocessing Wastes
Strong Base [SB] Weak Acid [WA] Impacts on HLW and LAW Glass Dissolution
Structures and Properties of Spinel MgAl2O4/Glass Interfaces from Molecular Dynamics Computer Simulations
Sulfur Incorporation into Sodium Borosilicate Glasses
Understanding the Influence of Melt Chemistry on Nucleation and Growth of Spinels in High-level Nuclear Waste Glasses
Vitrification HLW Containing A High Concentration of Molybdenum


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