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Meeting 2023 TMS Annual Meeting & Exhibition
Symposium Ceramic Materials for Nuclear Energy Research and Applications
Presentation Title Zirconia-coated uranic fuel particles processing and in situ sintering characterisation
Author(s) Phylis Makurunje, Gareth Stephens, Simon C. Middleburgh
On-Site Speaker (Planned) Phylis Makurunje
Abstract Scope Gel casting was studied as an encapsulation-aiding process for the manufacture of uranic coated fuel particles (CFP) for gas and light water reactors. Encapsulation involved the envelopment of colloidal droplets within a zirconium oxynitrate precursor solution during gel casting. The enveloping zirconium oxynitrate precursor phase was to result in a zirconium oxide coating on uranium dioxide kernels. The surfactants-conditioned uranium dioxide colloid was modified by an alginate cross-linking matrix prior to encapsulation, to facilitate solidification by ion exchange when contacted with calcium chloride. Pourbaix diagrams were employed to analyse zirconium oxynitrate solution stability with varying pH and complemented by experimental zeta potential studies. The kernels' sintering behaviour and thermal expansion were analysed by an optical dilatometer system up to 1600 C in argon and characterised by XRD, Raman spectroscopy and SEM. Encapsulated wet granulation is a promising method for manufacturing coated fuel particles.
Proceedings Inclusion? Planned:
Keywords Surface Modification and Coatings, Ceramics, Shaping and Forming

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advanced Characterization and Modeling of Nanoprecipitates in Spent Nuclear Fuel
Atomic scale simulation of amorphous intergranular films in nuclear fuel materials
Atomistic-scale simulations used to simulate creep in oxide fuel
Atomistic and mesoscale modeling of fission gas and fission products diffusivity in TRISO fuel kernels
Atomistic investigation of radiation-induced defects in ThO2
Cluster dynamics modeling of defects and fission gas in Gd doped UO2 under irradiation
Comparison of the electronic transport of UN and ThN versus ThC
Comprehensive characterization of damage in ion irradiated ceramics for validation of atomistic models
Defect chemistry and radiation stability of (Gd & Zr) co-doped UO2
Development of UC/UO2 Composite Fuels for Light Water Reactors
Diffusion properties in uranium-plutonium mixed oxides: atomic scale investigation of the effect of composition and chemical disorder
Emulation of Microstructures and Tritium Behavior in Lithium Aluminate by Ion Irradiation
Hidden defect evolution mechanism in ThO2 revealed by atomistic modeling
High-Entropy Carbide Ceramics: New Materials for Extreme Environments in Nuclear Energy Applications
Impact of Resonance Scattering on the Thermal Conductivity of ThO2
Improving uranium mononitride behaviour using uranium diboride addition
Irradiation- and dopant-induced structural changes in ceramic nuclear fuels probed via elastic and optical properties
Low-temperature fabrication of ceramic tritium breeder materials, for enhanced control of microstructure and phase formation
Microstructural characterization of neutron irradiated concrete minerals
Microstructural, Mechanical and Thermal Characterization of High Entropy Carbide Ceramics
Modelling the melting temperature of CrUO4 to assess its behaviour during the sintering of Cr-doped UO2
Multiphysics Modeling of High Burnup UO2 at Mesoscale
Multiscale Modeling for High-burnup Structure Formation in UO2
Oxidation Behavior and Mechanisms of the SiC Coating in TRISO Fuel Particles
Phase equilibria and thermodynamics of tri-carbide fuels for nuclear thermal propulsion
Predicting mechanical behavior of Uranium oxide fuel pellets using full-field defect diffusion modeling in a crystal plasticity framework
Quantifying irradiation-induced defects in SiC and WC through stored energy measurements of radiation damage
Quantifying the impact of fast interface diffusion and free surface evolution on fission gas release in UO2 using a phase-field model
Radiation Damage in Lithium Oxide, a Surrogate for Beryllium Carbide
Radiation damage of ion-irradiated high entropy ceramics
Radiation shielding ceramics with enhanced performance and scalability
Radiation studies on the TiZrNbHfTa high entropy alloy and its hydrides.
Relating Microstructural Evolution and Stoichiometry to Tritium Release from Ternary Lithium Ceramics
Revealing The Microstructure and Irradiation Effects on UO2 Fracture Via Coupled Phase-Field and MD Simulations Approach
Scanning Transmission Electron Microscopy of Nanoprecipitates in Spent UO2 Nuclear Fuel
Silica Formation on SiC Following Steam Attack
Simulation of irradiation-induced bubble over-pressurization and application in fuel performance
Soft X-ray Synchrotron Radiation Spectromicroscopy of Spent Nuclear Fuel Focused Ion Beam Sections
Surface Modification Strategies for Hydrogen Retention in Hydride Moderators
Susceptibility of Nuclear Fuel Ceramics to Oxidation and Hydridization during Off Normal Events
Thermomechanical characterization of advanced reactor alloys and composites exposed to high-temperature gas environments
Uranium Silicide Processing for Advanced Reactors
Zirconia-coated uranic fuel particles processing and in situ sintering characterisation

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