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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 In-Situ XRD Study of Alloy 709's Mechanical Behavior for Advanced Fast Reactor Applications
Author(s) Dominic Piedmont, Donghee Park, Victoria Riso, Xiang Liu, James Stubbins
On-Site Speaker (Planned) Dominic Piedmont
Abstract Scope In-situ XRD information on Alloy 709’s mechanical response at various temperature and strain rate regimes was collected. From the resulting tensile tests, an optimized constitutive equation was developed. The simultaneously collected Wide and Small Angle X-ray Scattering (WAXS/SAXS) data was used to support the material representation given in the models. WAXS data revealed dislocation behavior and the presence of a secondary phase which resulted in load partitioning. Whereas, SAXS data was used to observe the volume fraction of phases as well as voids and their associated evolution and growth. With support from XRD analysis, an understanding and justifications for the resulting deformation constants within constitutive equations can be established. A complete picture of Alloy 709’s microstructural response to various temperature and strain rate deformation regimes is constructed from three observables: phase-based peak broadening, phase-based lattice strain, and void volume evolution, which are captured in an optimized set of constitutive equations.
Proceedings Inclusion? Planned:
Keywords Mechanical Properties, Nuclear Materials, Iron and Steel

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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