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Meeting MS&T22: Materials Science & Technology
Symposium Ceramics for a New Generation of Nuclear Energy Systems and Applications
Presentation Title Integration of Nuclear Fuel and Embedded Sensors within Additively Manufactured SiC Components
Author(s) Christian Petrie
On-Site Speaker (Planned) Christian Petrie
Abstract Scope The adoption of silicon carbide (SiC) ceramic components within nuclear reactor designs has historically been limited due to challenges in manufacturing components with complex geometries. Oak Ridge National Laboratory has recently demonstrated an additive manufacturing (AM) process to overcome these challenges using binder jet 3D printing of SiC components that are densified using chemical vapor infiltration. Leveraging this process, the Transformational Challenge Reactor (TCR) fuel form was conceptualized to include a dense packing of conventionally fabricated uranium nitride tristructural isotropic fuel particles within an AM SiC matrix. This same process is used to embed sensors at critical locations within 3D printed SiC fuel forms or structural components. This presentation will provide an overview of the SiC AM and sensor embedding processes, the challenges and opportunities for designing, fabricating, and instrumenting TCR-like fuels, and the results from initial irradiation testing of integral fuel compacts.

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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