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Meeting 2021 TMS Annual Meeting & Exhibition
Symposium Characterization of Nuclear Materials and Fuels with Advanced X-ray and Neutron Techniques
Presentation Title Evolution of Stresses in Deformation Twins in the Plastic Zone Using Three-dimensional Synchrotron X-ray Diffraction
Author(s) Hamidreza Abdolvand, Karim Louca, Charles Mareau, Marta Majkut, Jonathan Wright
On-Site Speaker (Planned) Karim Louca
Abstract Scope Hexagonal closed-packed (HCP) metals have been extensively used in various industrial sectors. Understanding the deformation mechanisms of HCP metals at the grain-scale is a necessity for developing predictive models that can be used for the performance or failures analysis of engineering components. One of the common deformation mechanisms in HCP metals is deformation twinning. In this study, average grain stresses and size of the tensile twins are investigated with respect to their parent grains. In-situ three-dimensional X-ray diffraction (3D-XRD) is used for capturing grains center-of-masses (COMs), orientations, strains, and volumes. The evolution of stresses in twin and parent pairs are studied in detail, both at the early stages of plasticity and further into plastic zone.
Proceedings Inclusion? Planned:
Keywords Characterization, Nuclear Materials, Other

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

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 Microstructure, Texture, And Residual Stress in a Neutron Irradiated CANDU Pressure Tube
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
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
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
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

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