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Meeting 2021 TMS Annual Meeting & Exhibition
Symposium Characterization of Nuclear Materials and Fuels with Advanced X-ray and Neutron Techniques
Sponsorship TMS Structural Materials Division
TMS: Advanced Characterization, Testing, and Simulation Committee
TMS: Nuclear Materials Committee
Organizer(s) Xuan Zhang, Argonne National Laboratory
Jonathan Almer, Argonne National Laboratory
Maria A. Okuniewski, Purdue University
Joshua J. Kane, Idaho National Laboratory
Donald W. Brown, Los Alamos National Laboratory
J. Rory Kennedy, Idaho National Laboratory
Arthur T. Motta, Pennsylvania State University
Scope Neutron and x-ray radiation sources offer new opportunities to advance the fundamental understanding of nuclear reactor materials, fuels and engineering components. A variety of advanced characterization tools including diffraction, imaging and spectroscopy have recently become available to allow measurements of microstructure and deformation over a range of relevant time and length scales, on both pre- and post-irradiated materials, and under in situ conditions including stress, corrosive media and temperature. The symposium will highlight recent experimental efforts and future prospects to characterize material and fuel systems for nuclear reactor applications using neutron and x-ray radiation techniques. Areas covered will include stress/strain evolution, void and crack initiation and propagation, structural stability, phase stability and transformations, characterization of irradiation defects, and corrosion. Specifically, the following areas are encouraged:

• In situ studies of dynamic processes including deformation, phase transformations, recrystallization and corrosion.
• 3D imaging based on diffraction, phase, density, or elemental contrast.
• Characterization of irradiation-induced effects.
• Experimentation coupled with modeling.
Abstracts Due 07/20/2020
Proceedings Plan Planned:
PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE

4D X-ray Diffraction Microscopy Study of Tensile Deformation of Neutron-irradiated Fe-9Cr Alloy
Advanced Characterization of Nuclear Fuel Using Neutron Imaging
Characterization of Irradiated Nuclear Fuels with Pulsed Neutrons
Characterization of long range ordering in Ni-based alloys with ex-situ and in-situ synchrotron x-ray diffraction
Characterization of Nuclear Energy Materials in 2D and 3D using Laboratory-based X-ray Microscopy
Characterization of the crystal structure evolution of U-Zr alloys utilizing time-of-flight neutron diffraction with in-situ-heating
Characterization of U-10Zr Microstructures Using Synchrotron Radiation in Preparation for Irradiation Testing in the Advanced Test Reactor
Creep Behavior of Advanced Austenitic (Fe-25Ni-20Cr) Alloy 709 through in-situ neutron diffraction characterization and Transmission Electron Microscopy characterization
Evolution of stresses in deformation twins in the plastic zone using three-dimensional synchrotron X-ray diffraction
Getting “Around” the High Mass Attenuation Issue for μX-ray Computed Tomography of Nuclear Fuels
Grain-scale Micromechanical Response of a Zr Alloy Using High Energy Diffraction Microscopy and Crystal Plasticity Simulations
Identifying the Microstructural Origins of Creep Damage in Alloy 617
In-situ investigation into the stability of hydride phases in zirconium
In-situ synchrotron X-ray diffraction study on tensile deformation of neutron irradiated Fe-Cr-C alloys
In-Situ XRD Study of Alloy 709's Mechanical Behavior for Advanced Fast Reactor Applications
Irradiation-induced Effects in HT-UPS steel Using Far-field X-ray Diffraction and Grain Tracking Analysis
Irradiation effects on precipitate distributions in high-temperature ultrafine-precipitate-strengthened steel characterized by synchrotron micro-computed tomography
Microstructural Characterization of the Stress and Strain Deformation Partitioning Evolution in Tungsten Heavy Alloys
Microstructure and crystal structure studies in the U-Zr system
Multimodal Synchrotron Characterization of Transmutation Products in Structural Materials
Neutron Imaging at LANSCE: Characterizing Nuclear Materials for Next Generation Reactor Designs.
Neutron Radiography Capabilities at LANSCE: Completing LANSCE's Cold/Thermal/Epithermal Imaging Suite With Fast-Neutron Radiography
Non-destructive characterization of Nuclear Materials using Neutron Imaging Techniques
Non-destructive Correlative 3D Characterization of Nuclear Graphite: From the Microscale to the Nanoscale
Non-Destructive Evaluation of Irradiated Nuclear Fuel by Neutron Imaging
Synchrotron High-energy X-ray Studies of Nuclear Reactor Materials
Synchrotron Microdiffraction Study of Cracks and Indentation on UO2 Material
Transmission Spectrum Estimation and Material Decomposition with Energy Resolved Neutron Imaging
Using in-situ synchrotron x-ray scattering to determine the TTT diagram of U-6Nb
X-ray based nanodiffraction to study strain in materials for nuclear energy
X-Ray Diffraction-Computed Tomography (XRD-CT) Facility at NSLS-II for Studying Materials for Nuclear Applications


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