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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 Non-destructive Characterization of Nuclear Materials using Neutron Imaging Techniques
Author(s) Hassina Z. Bilheux, Yuxuan Zhang, Jean C Bilheux, Erik Stringfellow, Kristian Myhre, Brianne J Beers, Brent Heuser, Tommy Thomasson, Amy Jones, Richard Ibberson
On-Site Speaker (Planned) Hassina Z. Bilheux
Abstract Scope Non-destructive characterization of nuclear materials such as cladding materials or nuclear fuels are often difficult to perform due to the scarcity of samples prepared under conditions similar to commercial reactor environments, but also because handling some of these materials at a research facility (where neutrons sources are often located) requires special radiation precautions. In addition, penetration through high-Z materials in nuclear fuels causes a major challenge for most probing techniques. Neutrons are sensitive to light elements such as hydrogen and are not easily attenuated by heavy elements. Hence, neutron scattering techniques offer a unique insight into materials that are critical to nuclear industry. At research reactors, neutron computed tomography is a 3D technique capable of identifying defects such as cracks and porosity, but also the presence of hydrogen in cladding material for example. Spallation neutron sources offer unique neutron-wavelength dependent characterization capabilities (i.e. the material’s crystalline structure and isotopic content). -- Acknowledgements: This research used resources at the Spallation Neutron Source and the High Flux Isotope Reactor, U.S. Department of Energy (DOE) Office of Science User Facilities operated by the Oak Ridge National Laboratory. -- Notice of Copyright: This abstract has been authored by UT-Battelle, LLC, under Contract No. DE AC05-00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Characterization,

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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