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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 Investigation into The Stability of Hydride Phases in Zirconium
Author(s) Fei Long, Nima N. Badr, Matthew Topping, Igor Cherubin, Jun-Sang Park, Mark R. Daymond
On-Site Speaker (Planned) Fei Long
Abstract Scope High energy synchrotron x-ray diffraction in-situ heating/cooling has been used to study the dissolution/precipitation behavior of hydrides in Zr and its alloy systems. The stability of hydride phases, in particular the commonly observed delta and gamma hydrides, were studied by thermal cycling under a slow temperature ramp, in pure Zr, Zircaloy-2, and Zr-2.5Nb alloy. It is found that gamma phase is the low temperature stable phase in the binary Zr-H system, with delta phase precipitating first as the high temperature phase. In Zr alloys, however, the stability of delta extends down to room temperature; if there is any transformation to gamma it appears very sluggish. In-situ hydrogen ingress tests were conducted for a Zr-2.5Nb sample with hydride layer on two lateral surfaces, through which the memory effect of hydride precipitation is addressed.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Phase Transformations, 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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