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Meeting MS&T24: Materials Science & Technology
Symposium Ceramic Materials for Nuclear Energy Systems
Sponsorship ACerS Energy Materials and Systems Division
TMS: Nuclear Materials Committee
Organizer(s) Lingfeng He, North Carolina State University
Krista Carlson, University of Nevada, Reno
Theodore Besmann, University of South Carolina
Charmayne E. Lonergan, Missouri University of Science and Technology
Jake W. Amoroso, Savannah River National Laboratory
Brian J. Riley, Pacific Northwest National Laboratory
Kaustubh K. Bawane, Idaho National Laboratory
Joshua T. White, Los Alamos National Laboratory
Christian Deck, General Atomics
Gordon James Thorogood, Australian Nuclear Science and Technology Organization
Scope Advanced ceramics are attractive for next generation nuclear energy systems as they increase the operating temperature window to allow higher thermal efficiency, and exposure to variable environments. Although ceramic nuclear fuels have been widely used in current nuclear reactors, advanced energy systems call for improved materials with optimized properties. As an example, ceramic coatings are under active research to improve accident tolerance of nuclear fuels. Ceramic materials also contribute to enhanced safety of nuclear systems such as neutron moderation and shielding materials. High entropy ceramics and advanced composites are promising options for advanced nuclear applications.  Moreover, glass/ceramic/cement/geopolymer compounds have been applied in long-term waste disposal. Processing, properties, testing and accelerated qualification of ceramic materials need to be expanded to meet the future needs of the nuclear industry. This symposium focuses on experimental and computational studies of ceramics for nuclear energy research and applications.

Abstracts are solicited in, but not limited to, the following topics:

• Materials Design, Synthesis/Processing, Additive Manufacturing, Accelerated Materials Qualification (including ceramic fuels, ceramic coatings, glass/ceramic waste forms and inert matrix fuels)
• Vitrification Technologies and Radioactive Waste Immobilization
• Radiation Damage Effects, Chemical Compatibility and Corrosion, Thermophysical Property
• High Entropy Ceramics and Advanced Composites for Next-Generation Nuclear Applications
• Materials for Molten Salt Reactor Application
• Neutron Moderation and Shielding Materials
• Synergistic Multi-scale Modeling and Experimental Study on Microstructure Evolution, Mechanical and Physical Properties of Ceramics in Nuclear Energy Environments

Abstracts Due 05/15/2024

Advanced FCCI Barrier Coatings: Enhancing Fuel Cladding Performance Against Metallic Fuels at High Temperatures
Advanced Moderator Module (AMM) Manufacturing
Analysis of Crucible-Scale Corrosion Testing of Monofrax® K-3 Refractory in Contact with Glass Melts
Assessing High Uranium Density Ceramic Fuels for Implementation in Water Cooled Reactors
Atomic Scale Order in Swift Heavy Ion Irradiated MgAl2O4 Spinel Oxide
Atomistic Investigation of Defects and Defect-Phonon Scattering in ThO2
Beyond TRISO: Development of New Coated Particle Fuels
Challenge of Making Accurate Heat Capacity Measurements for Fluoride Salts
Characterization and Thermal Stability of (Li,Na,K)2O-Fe2O3-P2O5 Glasses for Waste Immobilization.
Chemical Durability of Cermet Waste Forms for Advanced Reactor Wastes
Chemical Thermodynamic Database Development and Applications for Molten Salt Reactors
Cluster Dynamics Simulations of Tritium and Helium Diffusion in Lithium Ceramics
Composition and Properties of Iron Phosphate Waste Forms for Radioactive Salt Waste Immobilization
Compositionally Complex Carbide Ceramics: A Perspective on Irradiation Damage
Corrosion Behavior of Nuclear Waste Glasses and Glass-Ceramics in Geological Repository Systems
Determining Waste Glass Corrosion via the EPA Method 1313, the Stirred Reactor Coupon Analysis, and Vapor Hydration Testing
Development of Kernel Fuels for High Temperature Gas Reactor and Space Systems
Developments in Producing Pyrolytic Carbon Coatings for Advanced Particle Fuel Forms
High-Burnup Structure Formation and Associated Fission Product Diffusion in UO2
High Temperature Ceramic Nuclear Fuels for Cross-Cutting Applications
Indirect Powder Bed Fusion of Ceramics for Neutron Radiation Shielding
Investigation of Technetium Management through Chalcogenides and Bimetallic Nanoparticles
Ion irradiation of UC and UN and their surrogates
Iron Phosphate Glasses for Waste Immobilization
Irradiation Study of TiN Inner-Wall Coating for Advanced Cladding to Suppress FCCI
Mechanisms Controlling Defect Evolution in Irradiated CeO2 Using In-Situ TEM Annealing
Microstructural Characterization and Thermal Oxidation of Zr Doped UO2
Molecular Dynamics Simulations of Displacement Cascades in LiAlO2 and LiAl5O8 Ceramics
MXene Hybrids as Promising Candidates for Iodine Gas Capture
Numerical Modeling of Graphite Oxidation In Water Vapor Ingress Accidental Conditions for High Temperature Gas-Cooled Reactors
Oxidation Behavior of the SiC Coating of TRISO Fuel Particles in Air or Water Vapor
Performance of CrAl/Al2O3 Multilayer H2 Permeation Barrier Designed for High Temperature Metal Hydride-Based Neutron Moderators
Phase Equilibria and Thermodynamics of Uranium Mononitride Fuel Undergoing Burn-Up in a Lead-Cooled Reactor
Phosphate-Based Dechlorination of Electrorefiner Salt Waste Using a Phosphoric Acid Precursor
Post-irradiation Examination of Irradiated Fuels with Pulsed Neutrons at LANSCE
Predicting the Durability of Nuclear Waste Immobilization Glasses Using Nonparametric Machine Learning
Progress on Modeling Refractory Corrosion of Waste Glass Melters
Protecting Structural Components in Molten Salt Nuclear Reactors with Functional Coatings.
Room Temperature Micro-Cold Spray of Ceramic Thick Films
Statistical Fracture Behavior of Doped UO2 Using a Ball-On-Ring Test Method
Structural Analysis of Swift Heavy Ion Irradiated β-Sc2Hf7O17 and γ-Sc2Hf5O13
Structural Manipulation of Ceramic Materials via Extreme Conditions
Thermal Diffusivity of UN Produced via Carbothermic Reduction Prior to Nitriding
Thermodynamic Modeling of the LiF-NaF-(La,Ce,Pu)F3 Systems for Molten Salt Reactor Applications
Time-Temperature-Transformation Diagram Development for a Coupled-Operation Glass Composition with SWPF

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