ProgramMaster Logo
Conference Tools for MS&T23: Materials Science & Technology
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools
About this Symposium
Meeting MS&T23: Materials Science & Technology
Symposium Ceramics for New Generation Nuclear Energy System Application
Sponsorship TMS: Nuclear Materials Committee
Organizer(s) Ming Tang, Clemson University
Krista Carlson, University of Nevada, Reno
Maik K. Lang, University of Tennessee
Jake W. Amoroso, Savannah River National Laboratory
Brian J. Riley, Pacific Northwest National Laboratory
Lingfeng He, North Carolina State University
Enrique Saez, Clemson University
Jinsuo Zhang, Virginia Polytechnic Institute and State University
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/ceramic coatings are under active research to improve/enhance structural materials’ performance. Ceramic materials also contribute to enhanced safety of nuclear systems including light water reactors due to their high temperature stability. Moreover, glass/ceramic/cement/geopolymer compounds have been applied in long-term waste disposal. Processing, properties and testing 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.

Proposed Scopes (but not limited to):

• Materials (ceramic fuel, ceramic coating, glass/ceramic waste form) Design, Synthesis/Processing
• Advanced Materials and Manufacturing for Next Generation Reactors
• Advanced Characterization Techniques
• High Entropy Ceramics
• Vitrification Technologies and Radioactive Waste Immobilization
• Radiation Damage Effects, Chemical Compatibility and Corrosion, Thermophysical Property,
• Materials for Molten Salt Reactor Application
• Synergistic Multi-scale Modeling and Experimental Study on Microstructure Evolution and Physical Properties of Ceramics in Nuclear Energy Environments

Abstracts Due 03/15/2023
Proceedings Plan Undecided
PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE
No additional information can be displayed at this time.


Questions about ProgramMaster? Contact programming@programmaster.org