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Meeting MS&T23: Materials Science & Technology
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments IV
Presentation Title Advanced In-situ Strain Mapping for Zr Oxidation by 4D-STEM
Author(s) Yongwen Sun, Yang Yang, Ying Han, Dan Zhou, Hugo Perez Garza, Alejandro Gomez Perez, Thanos Galanis
On-Site Speaker (Planned) Yongwen Sun
Abstract Scope Zirconium alloy fuel cladding undergoes oxidation in nuclear reactors, which weakens its mechanical strength and increases the likelihood of failure. Effective strain mapping is critical for understanding strain anisotropy due to zirconium oxidation and prompting the development of oxidation mechanism theory. Here, we developed an in-situ strain mapping method to study the oxidation in zirconium, by integrating four-dimensional scanning transmission electron microscopy (4D-STEM), advanced gas-cell-holder, precession electron microscopy and direct electron detector. The key to successful strain mapping by our method lies in ensuring high signal-to-noise ratio in the nano-beam electron diffraction patterns. The effect of gas pressure, sample thickness and electron beam precession will be discussed. Our approach facilitates high-quality strain mapping across a large field of view during zirconium oxidation with nanometer resolution. This proposed technique has significant implications for a wide range of corrosion studies, enabling more insights into the chemo-mechanical evolutions in materials under extreme environments.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Accelerated Assessment of Microstructure-Mechanical Property Relationships in Ni Based Superalloys
Accelerated Creep Testing for High-Temperature and Nuclear Applications
Advanced In-situ Strain Mapping for Zr Oxidation by 4D-STEM
Assessing the Ability of Nuclear Fuel Performance Codes to Predict Radially Resolved Properties in Oxide Fuels
Capturing 3D Evolution of Twin Networks in Titanium as a Function of Applied Strain
Effect of Solutes on the Radiation Induced Segregation in Ferritic Alloys at ∑3- grain Boundaries
Effect of Strain Rate on Tensile Properties of C250 Maraging Steel
Enabling Multiscale Materials Characterization with Machine Learning
Four-dimensional Scanning Transmission Electron Microscopy (4D-STEM) Characterization of Intergranular Corrosion of Austenitic Stainless Steels in Lead-bismuth Eutectic
High-Temperature Irradiation Behavior of Piezoelectric Aluminum Nitride
In Situ SEM Nanomechanics at Cryogenic Temperatures
Interdiffusion Behaviour of UN with Zircaloy-4 via Diffusion Couple Studies
M-1: Novel Method for Fabricating and Analysis of 3D Printed Composite for Radiation Shielding Containing Metalized Halloysite Nanotube
Mapping Elemental Distributions Across Thin Corrosion Films Formed on Nuclear Reactor Core and Structural Materials via Ex-situ And In-situ Atom Probe Tomography
Multimodal Characterization of Materials Corrosion in Molten Salts
Phase Stability of Delta-ZrH Under Ion Irradiation
Probing Nanoscale Properties of Radioactive Material by Advanced Correlative Microscopy
STEM-based Mapping of Nanoscale Point Defects Produced via Temperature, Irradiation, And Corrosion
Structural Stability of REE-PO4 (REE=Sm,Tb) under Swift Heavy Ion Irradiation
Thermodynamic Modeling and Calculation of Phase Formation Processes Under Irradiation Conditions of Uranium-plutonium Nitride Fuel
Transition Metal Carbonitride Materials Exposed to Swift Heavy Ions

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