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Meeting 2021 TMS Annual Meeting & Exhibition
Symposium Ceramic Materials for Nuclear Energy Research and Applications
Presentation Title Microstructural and Fission Products Analysis from Irradiated UO2 Fuel Using Atom Probe Tomography
Author(s) Mukesh Bachhav, Lingfeng He, Brandon Miller, Xiang Liu, Fabiola Cappia, Jian Gan
On-Site Speaker (Planned) Mukesh Bachhav
Abstract Scope The distribution of solid and volatile fission product species has not been well characterized for UO2, however, because of the fine scale of precipitates and the possibility for dilute solid solutions fission product elements with the fuel alloy. Atom Probe Tomography (APT) provides a methodology to characterize spatial location and elemental composition of materials in three dimensions with near atomic-resolution high-resolution information is achieved through ion-by-ion field evaporation. Moreover, the development of shielded Focused Ion Beam instruments present unique opportunities presented for site-specific analysis for irradiated nuclear fuels using APT. The microstructure, composition, chemical and physical states of fission products, including metal and oxide precipitates and fission gas bubbles in irradiated ceramic fuels have been characterized using APT, Atomic-Resolution Scanning Transmission Electron Microscope equipped with energy dispersive X-ray spectroscopy system at Idaho National Laboratory. Findings of this work will be presented.
Proceedings Inclusion? Planned:
Keywords Characterization, Nuclear Materials, Ceramics

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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