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Meeting MS&T22: Materials Science & Technology
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments III
Presentation Title Hydrogen Dynamics in Yttrium Hydride Moderator Material
Author(s) James Torres, Alexander Long, Dale Travis Carver, Sven Vogel, Aditya Shivprasad, Tyler Smith, Caitlin Taylor, Erik Luther, Holly Trellue
On-Site Speaker (Planned) James Torres
Abstract Scope A compact, nuclear microreactor that utilizes low-enriched uranium fuel is a promising solution to meet US energy demands for remote (e.g., space) and highly dense population areas. Yttrium hydride (YH) is the candidate moderator material for the microreactor design, chosen based on its superior retention of hydrogen at high temperatures. To date, there is a dearth of knowledge on hydrogen diffusion properties in YH. Hydrogen-mapping capabilities via neutron imaging are currently under development at the Los Alamos Neutron Science Center (LANSCE) with the goal to characterize hydrogen diffusion in YH samples as a function of stoichiometry, temperature, and phase fraction at both ambient and extreme environments (temperature gradients). Herein, we share our recent progress in technique development and include initial results from concentration- and temperature-gradient measurements from LANSCE. Additional measurements planned for Q4 of FY22 may also be discussed.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advanced In-situ and Post-Irradiation-Examination Thermal Conductivity Measurements of Nuclear Fuels and Materials
Advanced Synchrotron Characterization of Fission and Fusion Energy Materials
Applications of Cryogenic Nanomechanical Testing
Automated In Situ Deformation Characterization via Analytical SEM during High Temperature Tensile Testing
Characterization of Simultaneous High-energy Proton and Spallation-Neutron Radiation Effects in Structural Alloys
Correlating Irradiation Defect Models to Thermal Conductivity Evolution under Irradiation in ThO2
Defect Structure and Property Evolution in Ion-irradiated Tungsten: Progress towards a Comprehensive Understanding
Deformation Twinning versus Slip in Ni-based Alloys, Containing Pt2Mo-structured, Ni2Cr-typed Precipitates
Detection of Radiation Vulnerability in Microelectronic Systems
Dose Rate Dependent Radiation Enhanced Diffusion in Model Oxides
Elucidating Helium Induced Softening in Nanograin Tungsten Through Electron Microscopy Informed Synchrotron X-Ray Scattering
Europium 3+ as a Structural Luminescent Probe in Calcined Ceria Pellets
High-temperature Stable Nanolamellar Transition Metal Carbides Derived from Two-dimensional MXenes for Extreme Environments
Hydrogen Dynamics in Yttrium Hydride Moderator Material
In-situ Thermal Diffusivity Recovery and Defect Annealing Kinetics in Self-ion Implanted Tungsten Using Transient Grating Spectroscopy
In Situ Irradiation of TiO2 Nanotubes
In Situ Monitoring of Heavy Liquid Metal and Molten Salt Corrosion under Irradiation with Proton-induced X-ray Emission (PIXE) Spectroscopy
Machine Learning Algorithms for High-throughput Characterization of Structure and Microstructure of Metals for Extreme Environments
Materials in Extreme Environments Investigated with Positron Spectroscopy
Microstructural Evolution of Alloy 718 under High Temperature In-situ Ion Irradiation with Machine Learning
Neutron Imaging at LANSCE: Characterizing Materials for the Next Generation of Nuclear Reactor Designs
Probing Short-Range Order in Disordered Crystalline Materials for Extreme Environments
Radiation Resistance of Metallic Glass Coatings of Crystalline Nanostructures
Recent Innovations in Machine Learning-based Techniques for In-situ Microscopy Data Analysis
Ring Pull Testing: The Effect of Mandrel Diameter
Thermomechanical Characterization of Advanced Reactor Materials in High Temperature Gas Environments
Three-dimensional Characterization of Multiple Phase Regions within a Neutron Irradiated U-Zr Fuel
Utilizing In-situ Microscopy Techniques to Decipher the Micro-scale Dynamics of Materials in Extreme Environments

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