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Meeting MS&T22: Materials Science & Technology
Symposium Ceramics for a New Generation of Nuclear Energy Systems and Applications
Sponsorship TMS Nuclear Materials Committee
ACerS Energy Materials and Systems (EMSD) Division
Organizer(s) Ming Tang, Clemson University
Enrique Martinez Saez, Clemson University
Yongfeng Zhang, University of Wisconsin
Krista Carlson, University of Nevada, Reno
Yutai Katoh, Oak Ridge National Laboratory
Jean Paul Crocombette, CEA Saclay
Erofili Kardoulaki, Los Alamos National Laboratory
Levi Gardner, Argonne National Laboratory
Jian Zhang, Xiamen University
Charmayne E. Lonergan, Pacific Northwest National Laboratory
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 Sessions (but not limited to):
• Material Design, Synthesis, and Characterization
• Materials Processing, Joining and Coating
• Advanced Materials and Manufacturing for Next Generation Reactors
• High Entropy Ceramics
• Vitrification Technologies and Radioactive Waste Immobilization
• Radiation Damage Effects, Chemical Compatibility and Corrosion, Thermophysical Property
• Synergistic Multi-scale Modeling and Experimental Study on Microstructure Evolution and Physical Properties of Ceramics in Nuclear Energy Environments

Abstracts Due 05/15/2022
Proceedings Plan Undecided

A Physics-Based Cluster Dynamics Model of Radiation-Enhanced Growth of Oxides
Additive Manufacturing of Ceramics for Nuclear Applications
Bismuth Loaded Carbon Foam as an Effective Radio Iodine Sorbent
Characterization of Radiation Effects in Ceramics with Spallation Neutron Probes
Characterizing Effects of Aging Bismuth Laden Sorbents in NOx Atmosphere for Radioiodine Capture
Cluster Dynamics Simulations of Point Defects and Fission Gas Evolution in Irradiated Ceramic Nuclear Fuels
Comparison of ZrC-TZM Mechanical and Structural Properties Before and After Extended Carbon Exposure
Corrosion of SiC in Molten Salt and Liquid Lead
Development and Characterization of Ga/Ta Doped Li7La3Zr2O12 for Direct LiT Electrolysis
Development of Novel TRU-containing Ceramics for Nuclear Waste Immobilization
Environmental Degradation of Ceramic Materials in Nuclear Energy Systems
Evaluation of In-Flow Mechanical Robustness of Metal-Functionalized Porous Silica Materials
Fabrication and Properties of Sintered Yttrium Hydride
Integration of Nuclear Fuel and Embedded Sensors within Additively Manufactured SiC Components
Microstructural Evolution in Ceramic Nuclear Fuels and their Surrogates under Irradiation
Modeling Vibrational Modes in Raman Spectra of ThO2
Phonon Broadening in High Entropy Ceramic Carbide
Preparation of High Entropy Zirconate and Titanite Pyrochlores and Further Radiation Damage Study
Radiation Damage of Ion-irradiated High Entropy Ceramics
Radiation effects in single-crystal high-entropy oxides
SiC Oxidation and Irradiation Resistance in Advanced Nuclear Reactor TRISO Fuel
Single Component Variations in Glass Ceramic Waste Forms
Sulfur Retention of Low Activity Waste Glasses
Synthesis and Characterization of Super Occluded LiCl-KCl in Zeolite-4A as a Chloride Salt Waste Form Intermediate

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