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Meeting MS&T22: Materials Science & Technology
Symposium Ceramics for a New Generation of Nuclear Energy Systems and Applications
Presentation Title Additive Manufacturing of Ceramics for Nuclear Applications
Author(s) S. K. Sundaram
On-Site Speaker (Planned) S. K. Sundaram
Abstract Scope Additive manufacturing (AM) of ceramics can revolutionize rapid production of various materials for nuclear applications. Cerium oxide (ceria), fully stabilized 8 mol % yttria-stabilized zirconia (YSZ), and lithium silicate ceramics are studied using a Lithoz CeraFab 8500 lithography-based ceramic slurry 3D-printer to produce monolithic dense ceramic parts. Characteristics such as grain size, porosity, stoichiometry, and density were used to compare printed samples with traditionally processed and sintered counterparts. Main parameters varied are powder particle size, solid loading of the slurry, sintering temperature, and orientation of layers printed. Ceria powders with a particle size of 0.5 μm and slurry solid loading of 41.5 vol% produced high-density ceramics with complex structures and geometries with a maximum of 98% theoretical density. We achieved average theoretical density of 98 % for YSZ and 84 % for lithium silicate ceramics. The presentation will summarize our results, lessons learned, and potential for scale up.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

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 of Novel TRU-containing Ceramics for Nuclear Waste Immobilization
Environmental Degradation of Ceramic Materials in Nuclear Energy Systems
Fabrication and Properties of Sintered Yttrium Hydride
Integration of Nuclear Fuel and Embedded Sensors within Additively Manufactured SiC Components
J-1: Development and Characterization of Ga/Ta Doped Li7La3Zr2O12 for Direct LiT Electrolysis
J-2: Evaluation of In-Flow Mechanical Robustness of Metal-Functionalized Porous Silica Materials
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
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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