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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 Characterization of Long Range Ordering in Ni-based Alloys with Ex-situ and In-situ Synchrotron X-ray Diffraction
Author(s) Nicholas Steven Jude Aerne, David Sprouster, Fei Teng, Mehmet Topsakal, Adrien Couet, Kumar Sridharan, Julie D Tucker
On-Site Speaker (Planned) Nicholas Steven Jude Aerne
Abstract Scope The formation of long-range order in high-Cr, Ni-based alloys reduces the ductility of the microstructure. This loss of ductility is of concern to the service life of components (i.e. steam generator tubing) in pressurized water reactors. In this research, isothermal aging at temperatures between 330-475 C of model Ni-Cr, and commercial 690, 625, and 625P alloys has been performed up to 10,000 and 21,000 hours, respectively. Additionally, 10 alloys were proton irradiated to 1.5 dpa to enhance the Ni2Cr ordering. The alloys were characterized with ex-situ and in-situ synchrotron x-ray diffraction measurements. Ex-situ measurements were performed to reveal the microstructure evolution and quantification of the Ni2Cr ordering. In-situ experiments with temperatures up to 750 C were carried out to observe the critical transformation temperature. Preliminary results show lattice contraction at 15,000 hours aged at 475C in Alloy 690, indicative of Ni2Cr formation as seen in model alloys.
Proceedings Inclusion? Planned:
Keywords Phase Transformations, Nuclear Materials, Environmental Effects

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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
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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
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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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