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Meeting MS&T24: Materials Science & Technology
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments V
Presentation Title Nanoscale Redistribution of Lithium in Neutron Irradiated LiAlO2
Author(s) Edgar C. Buck, Shalini Tripathi, Gary J Sevigny
On-Site Speaker (Planned) Edgar C. Buck
Abstract Scope High-energy ion irradiation has been used to understand and predict neutron radiation effects in materials used in nuclear reactors. However, when the damage process involves both knock-on damage and transmutation, this method may fail to predict the damaged microstructure. LiAl5O8 has been reported from ion irradiation of LiAlO2 ceramics previously. However, LiAl5O8 is almost structurally identical to the cubic phase, γ-Al2O3. In this work, we show that x-ray diffraction of reactor irradiated Li6-enriched γ-LiAlO2 was inconclusive owning to the structural similarity of LiAl5O8 and γ-Al2O3. Modeling of electron diffraction suggested that specific reflections are forbidden in γ-Al2O3 but are present in LiAl5O8. Electron diffraction analysis of the irradiated ceramics suggested the occurrence of γ-Al2O3 in reactor irradiated LiAlO2. Direct observation of lithium was also attempted with Electron Energy-Loss Spectroscopy (EELS) and Energy-Filtered Transmission Electron Microscopy (EFTEM) which provided additional experimental evidence for the occurrence of γ-Al2O3.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advanced Characterization Capabilities of Nuclear Materials via NSUF
Advanced In-Situ Strain Mapping for Zr Oxidation by 4D-SPED
An In-Situ Transmission Electron Microscopy Study on the Synergistic Effects of Heating and Biasing of AlGaN/GaN High Electron Mobility Transistors
Application of Laboratory-Based Photoelectron Spectroscopy with Hard and Soft X-Rays to Nuclear Forensics Characterization of Uranium Dioxide Fuel
Atomic-Scale Hidden Point-Defect Complexes Induce Ultrahigh Irradiation Hardening in BCC Metals
Characterization of Aluminum Under Shock: Defects, Grain Orientation, and Phase Stability
Characterization of Radiation Damage in Nanocrystalline Ni- and Fe-Based Oxide Dispersion-Strengthened Alloys
Deciphering and Visualizing Helium Accumulation and Dynamics in Materials via In-Situ Characterization
Deployment and Testing of a Fiber-Based Instrument for In-Reactor Thermal Property Measurements at MIT Research Reactor
Determination of Molten Salt Thermal Conductivity Using Laser Flash Technique
Dynamics of Radiation Defect Accumulation in Non-Metallic Materials
Effect of Swift Heavy Ion Irradiation on Silicon Carbide
Formation and Recover of Dislocations Under Deformation and/or Irradiation of Elemental Tantalum, a Step Toward Understanding Complex BCC Alloys.
Impact of Amorphous Pockets on Displacement Damage Evolution in Crystalline Silicon
Influence of Defects Length-scale on Nuclear Graphite Properties
Interactions Between Radiation-Induced Defects and Shock in Al 1100
Investigation of Helium Bubble Formation at Tungsten-Dispersoid Interfaces in Dispersion-Strengthened Tungsten Alloys
Localized Crystallization of Zr Following Heavy Ion Irradiation of HfNbTaZr MPEA
Machine Learning and Molecular Dynamics-Coupled X-Ray Absorption Spectroscopy for Disordered Multicomponent Systems
Microstructural and Chemical Evolution Studies of U-10Zr Metallic Fuel and HT9 Cladding from Fast Flux Test Facility
Microstructural Evolution in 316L Stainless Steel Under Lead-Bismuth Eutectic Corrosion
Nanoscale Redistribution of Lithium in Neutron Irradiated LiAlO2
Neutron-Induced Reversible Nanostructuring of GeSe2
Quantitative Phase Characterization of Nuclear Cements and Concretes Using Non-Destructive 3D Automated Mineralogy and Enhanced Deep-Learning Reconstruction via X-ray Microscopy
Real-time Neutron Diffraction to Support Interpretation of DSC Results on Zr-2.5Nb for Reactor Pressure Tubes
Strong Dependence of 2D Material Radiation Tolerance on the Composition of the 2D Material and Its Surrounding Environment
Structural Characterization of Ultra-High Temperature Ceramics in Three Dimensions for Statistical and Physics-Based Modeling
Superimposed Effects of Texture and Grain Shape Anisotropy on Biaxial Creep Behavior of Nb-Modified Zircaloy-4 Cladding
Surface Microstructure Evolution and Associated High Temperature Anti-Oxidation Mechanisms of Copper with Vapor Deposited Graphene
Synthesis and Irradiation of Uranium Carbide and Nitride for TRISO Development
Thermophysical Characterisation of Zirconium-Based Nuclear Materials
Thermophysical Properties of Irradiated Yttrium Hydride Moderator Material
Tungsten-Based WTaVCr Refractory High Entropy Alloys for Fusion Energy Applications
Understanding Irradiation Assisted Hydrogen Embrittlement Using In Situ Coherent X-Ray Imaging
Understanding the Mechanism of Fission Gas Re-Solution and Blistering in UMo Fuel via Atomistic Modelling
Understanding the Surface and Near Surface via Nanomechanical Mapping

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