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Meeting 2021 TMS Annual Meeting & Exhibition
Symposium Ceramic Materials for Nuclear Energy Research and Applications
Presentation Title Influence of Dose Rate and Temperature on Mass Transport in Hematite
Author(s) Kayla Yano, Sandra D Taylor, Tiffany C Kaspar, Danny J Edwards, Daniel K Schreiber
On-Site Speaker (Planned) Kayla Yano
Abstract Scope In this study, mass transport pathways are directly visualized in an irradiated model iron oxide using novel isotopic tracer and characterization techniques. In nuclear reactor environments, irradiation-induced defects and elevated temperatures interact to influence mass transport. These two forces can be difficult to separate but we attempt to do so here. Isotopic tracers (e.g. 57Fe and 18O) are incorporated via molecular beam epitaxy. Irradiation dose rate and annealing temperature are varied to elucidate their role on atomic and nanostructural evolution. Complementary scanning/transmission electron microscopy and 3D atom probe tomography are used to document the microstructural changes and the diffusion of isotopic tracers in bulk and defected crystal structures. Comparisons are made of the isotopic redistribution upon either thermal annealing or argon irradiation to reveal the role of non-equilibrium point defect populations on self-diffusion coefficients. This study provides fundamental insight into mass transport mechanisms impacting material performance and degradation.
Proceedings Inclusion? Planned:
Keywords Characterization, Nuclear Materials, Environmental Effects

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

A Model of Grain Boundary Energy Anisotropy in Uranium Dioxide Nuclear Fuel
A Thermo-mechanical Coupled Phase Field Dynamic Fracture Model and Its Application in UO2
Comprehensive Treatment of Thermal Transport Under Irradiation in ThO2
Development of Hydrothermal Corrosion Barrier Coatings for High-density Nuclear Fuels
Development of Yttrium Hydride for High Temperature Moderator Application
Effect of UV and Gamma Irradiation on the Hydrothermal Corrosion of Ion-irradiated SiC
Electron Microscopy Characterization of the Fuel-cladding Interaction in Annular Fast Reactor MOX
Evolution of Ion Irradiated Nitride Ceramics Properties for Coated Particle Fuel Systems
Exotic Magneto-elastic Properties in Uranium Dioxide
Hydrothermal Corrosion of Silicon Carbide
Hydrothermal Corrosion Study of Additive Manufactured SiC Fibers
Impact of Dislocation Loops on Thermal Conductivity of CeO2
In-situ Measurement of Tritium Release from Lithium Aluminate Under Neutron Irradiation
Influence of Dose Rate and Temperature on Mass Transport in Hematite
Ionization Effects on Damage Accumulation Behavior in SiC
Irradiation Damage in High-entropy Carbide Ceramics
Irradiation Effects on Zirconium Alloy Oxides and Their Impacts on In-reactor Corrosion Rates
Microstructural Analysis and Micro-mechanical Testing on Xenon-irradiated Uranium Dioxide
Microstructural and Fission Products Analysis from Irradiated UO2 Fuel Using Atom Probe Tomography
Microstructural Characterization of Radiation Effects in 3D printed SiC
Microstructure and Chemical States of Fission Products in Irradiated AGR-1 and AGR-2 TRISO Particle UCO Fuel Kernels
Modeling of Pressure-driven Inter-granular Fracture in High Burnup Structure UO2 during LOCA Using A Phase-field Approach
Molecular Dynamics Investigations of AlN-based Piezoelectric Ceramics under Irradiation
Multiscale Modeling of High Burn-up Structure (HBS) Formation and Evolution in UO2
On the Role of Neutron Irradiation Damages on Fission Products Transport in the SiC Layer of TRISO Fuel Particles
Oxidation Behavior of TRISO Fuel Materials
Phase-field Modeling of Bubble Growth During High Burn-up Structure Formation in UO2
Radiation Tolerance of Nanoporous Gadolinium Titanate
Radiolytic Damage and Hydrogen Generation at Carbide – Water Interfaces
TEM Characterization of Dislocation Loops in Ion-irradiated Single Crystal ThO2
TMIST-3A Post-irradiation Examination
Towards a Model of Coupled Irradiation and Corrosion

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