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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 05/01/2024
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