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Meeting MS&T21: Materials Science & Technology
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments
Presentation Title Material Degradation Pathways of UO2 under Oxygen, Humidity, and Temperature Probed by XAFS
Author(s) Juejing Liu, Aiping Chen, Joanne Stubbs, Peter Eng, Hongwu Xu, Steven Conradson, Xiaofeng Guo
On-Site Speaker (Planned) Juejing Liu
Abstract Scope UO2 is the major component material for nuclear fuel rods for LWR or PWR. Understanding uranium oxide – water interfacial structures and chemical reactions are critical for addressing a wide range of high-profile issues in the nuclear fuel cycle, related to reactor fuel safety and geological disposal. Herein, we performed glazing incident X-ray absorption fine structure to probe changes of lattice structures of UO2 thin films under various humidity, oxygen level, and temperature conditions. Our preliminary results show that the UO2 lattice is distorted even in low humidity. Increasing humidity introduces two or three extra O atoms in the interstitial site (2.4~2.8 from U), suggesting the gradual formation of non-stoichiometric UO2+x or U4O9. This study provided an insight into the potential impacts of external conditions on UO2 from the atomic scale, which helped unveil all possible material degradation pathways.
Proceedings Inclusion? Undecided

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

A Closer Observation to the Precipitation Behavior of Proton Irradiated Dual Phase 308L Weldment Filler Materials
Characterization of Defects, Thermal Transport, and Elastic Properties in As-fabricated and Irradiated Single Crystal of ThO2
Characterization of Materials Exposed to Coupled Nuclear Environments Using Positron Annihilation Spectroscopy and Electrical Impedance Spectroscopy
Characterizing the Spatial and Temporal Evolution of Iron Thin Films during Coupled Irradiation and Corrosion
Correlated Scattering and Microscopy Techniques for In-situ and Ex-situ Rapid Clustering Determination in Activated Materials
Deep Learning Pipeline for Cavity Segmentation in Transmission Electron Microscopy
Development of In-situ Atomic Scale Defect Spectroscopy during Ion Irradiation
Effect of Dilute Magnetism in a Topological Insulator
Effect of Ion Irradiation on the Corrosion of 304SS in PWR Simulated Water Chemistry
Effects of He on Nanoscale Mechanical Properties of Er
Europa Lander Contamination Control: Materials Testing and Numerical Simulation in a Flight Like Environment
Femtosecond Laser Induced Surface Damages in Tungsten and Tungsten Carbide in High Heat Flux Conditions
Finding a Balance in FeCrAl Alloys: Utilizing Advanced Characterization, Testing, and Machine Learning to Balance Properties
High Temperature Mechanical Properties of WC/W2C Composites Fabricated by Reactive Sintering of Powders Colloidally Processed
Imaging Nanostructural Heterogeneities and Vacancy Supersaturation in Ni-20Cr after Corrosion in Molten Salt
In-situ Radiological Containment Sample Environments: A review of Capability and Compromises at X-ray and Neutron Sources
In Situ Ion Irradiation of Gadolinium Titanate: A Perspective on Microstructure and Memory
In Situ Transient Grating Spectroscopy for Rapid Radiation Tolerance Characterization
Insight into the Impact of Irradiation on Vibrational Properties of AlN Using Raman Spectroscopy
Material Degradation Pathways of UO2 under Oxygen, Humidity, and Temperature Probed by XAFS
Microstructural Characterization of Oxidized Tristructural Isotropic Particles (TRISO) in Various Gas Atmospheres
Modeling of Graphite Oxidation in Water Vapor Ingress Accidental Conditions for High Temperature Gas-cooled Reactors
Moduli Measurements of Fuels and Cladding Materials via Resonant Ultrasound Spectroscopy
Now On-Demand Only - Multi-scale Characterization of Silicon Carbide Oxidation
Optical Characterization of Defects in Proton Irradiated Fluorite Oxides
Prediction Thermo-physical Characteristics Nickel-based Superalloys Directional Crystallization
Radiation Damage Suppression in AISI-316 Steel Nanoparticles: Implications for the Design of Future Nuclear Materials
Real-time Thermal Oxidation Process of PFM Tungsten Under Fusion-relevant Conditions Revealed by In-situ Environmental TEM
Revealing Hidden Defects via Stored Energy Measurements of Radiation Damage
Richtmyer-Meshkov Instability Testing and Accompanying Analysis: A Surface Sensitive Approach to High Strain Rate Testing of Irradiated Material without Bulk Volumes
Speciation of Metal Ion Solutes in Molten Salt Matrices for Reactor Applications using Advanced Spectroscopy Techniques
Successful, Unsuccessful, and Partially-successful Attempts at Understanding Alloy Corrosion in Molten Salts
Tensile Performance of Diffusion Bonded AA6061-AA6061 Cladding-Cladding Interface for Application in U-10Mo Monolithic Fuel Plates
The Effect of Rotary Swaging on Zirconium Alloys and its Microstructure Property Correlation
Uncovering the Effect of Grain Boundary Dopants on Irradiation Induced Grain Growth Through In Situ Microscopy
Unraveling Solute-solvent Interactions in Molten Salt Environments Using X-ray Absorption Spectroscopy
Utilizing a Dynamic Segmentation Convolutional Neural Network for Microstructure Analysis

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