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Meeting MS&T22: Materials Science & Technology
Symposium Ceramics for a New Generation of Nuclear Energy Systems and Applications
Presentation Title A Physics-Based Cluster Dynamics Model of Radiation-Enhanced Growth of Oxides
Author(s) Aaron Kohnert, Edward Holby, Amitava Banerjee, Shivani Srivastava, Mark Asta, Blas P. Uberuaga
On-Site Speaker (Planned) Blas P. Uberuaga
Abstract Scope Materials intended for nuclear environments can experience a number of harsh conditions, including irradiation and corrosion. There is still relatively little known about how radiation-induced defects impact the corrosive growth of oxides. To remedy this gap, we have developed a cluster dynamics model that accounts for radiation-enhanced diffusion, the variability in charge states of defects as a function of the local electronic structure of the material, and the formation of space-charge regions that create electric fields and thus induce electromigration. Using this model, we demonstrate the impact of radiation damage on Fe2O3 hematite, where the defect thermokinetic parameters are determined using density functional theory and reproduce thermal oxide growth behavior. We find that irradiation has a large effect on oxide growth rates and that complex defect profiles evolve across the oxide. This work emphasizes the synergies between irradiation and corrosion.

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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