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Meeting MS&T24: Materials Science & Technology
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments V
Sponsorship TMS: Nuclear Materials Committee
Organizer(s) Cheng Sun, Clemson University
Caitlin A. Kohnert, Los Alamos National Laboratory
Cody A. Dennett, Commonwealth Fusion Systems
Samuel A. Briggs, Oregon State University
Michael Philip Short, Massachusetts Institute of Technology
Keyou Mao, Florida State University
Khalid Hattar, University of Tennessee Knoxville
Yuanyuan Zhu, University of Connecticut
Scope In the last decade, a wealth of new characterization methods, in-situ experimental techniques, and machine learning have emerged to drastically increase the speed and fidelity with which microstructure, and its dynamic evolution, can be characterized. This symposium solicits presentations that apply any of these advanced techniques to the study of materials structure, properties, and performance in irradiation and other extreme environments, e.g., nuclear energy and space applications. These technique advancements have occurred in areas including microstructural characterization, thermophysical property measurement, in situ measurements, and small-scale mechanical property testing. There is a specific interest in techniques that directly impact materials research for environments exhibiting high radiation fields, extreme temperatures, and corrosive or chemically reactive environments. In addition to the extremes present during routine operations, off-normal events, or transients, such as the aggressive thermal oxidation and decomposition of plasma facing components during air ingress accidents, call for rapid material innovations at this defining moment of rehabilitation for nuclear energy systems. The unique data provided by these advanced characterization tools also provide a new bridge to enhance the framing, refining, and validation of predictive models. With successful recurring in the past four years, the symposium of this year is expanded to include advanced data-driven methods in materials characterization.

Specific topics include, but are not limited to:
• Advanced data-driven methods in materials characterization.
• Novel destructive and non-destructive techniques for radiation damage characterization.
• Non-contact thermal and elastic measurement techniques.
• Non-standard mechanical property testing.
• Advanced diffraction techniques (X-ray, electron, or neutron) coupled to extreme environments.
In-situ observation of microstructural evolution under irradiation.
• Methods for monitoring corrosive attack in coolant environments.
• Studies of synergistic effects of these superimposed extreme environments on materials behaviors.
• Work enabling enhanced coupling of experimental with predictive modeling and simulation.

Abstracts Due 05/15/2024
PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE

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
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
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
L-1: Application of Laboratory-Based Photoelectron Spectroscopy with Hard and Soft X-Rays to Nuclear Forensics Characterization of Uranium Dioxide Fuel
L-2: Effect of Swift Heavy Ion Irradiation on Silicon Carbide
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
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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