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Meeting Materials Science & Technology 2020
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments
Presentation Title Mobility of Hydrogen in YH2 Probed by Nuclear Magnetic Resonance
Author(s) Scarlett Widgeon Paisner, Aditya Prahlad Shivprasad, Erik Paul Luther
On-Site Speaker (Planned) Scarlett Widgeon Paisner
Abstract Scope Metal hydrides are of interest for moderator materials in microreactors to improve efficiency of the fission reaction by thermalizing neutrons, allowing for minimization of the quantity of fuel required. Yttrium hydride (YH2-x) is an attractive option due to the high hydrogen content and the retention of the hydrogen beyond the operating temperature of 800 oC. However, the mobility of hydrogen at elevated temperature will impact the performance of these materials during operation. This study utilizes solid-state nuclear magnetic resonance spectroscopy (NMR) to determine the mobility of hydrogen in YH2-x powders as a function of temperature. YH2-x samples with different hydrogen contents were tested to investigate the role that stoichiometry has on the mobility. Preliminary data shows that a small fraction of hydrogen in YH1.80 is mobile at room temperature, and the fraction increases with temperature. The results will be discussed further in regards to hydrogen redistribution during reactor operation.

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In Situ Observation of Short- and Long-Timescale Material Property Evolution Under Extreme Conditions
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Characterization of Microstructure Evolution in Ceramic Materials Using Acoustic and Thermal Transport Measurements
Characterization of Stress and Environment Dependent Fracture Mechanisms of SiC/SiC CMCs
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Corrosion Control of Austenitic Stainless Steel and Nickel-Based Alloys in Molten Chloride Salt Environments
Design of a Hot Hydrogen Test Loop for Testing of Nuclear Thermal Rocket Elements
Development of a Combined Thermal Hydraulic and Materials Corrosion Liquid-Sodium Experimental Facility
Development of an In-Situ Mechanical Test System for Advanced Reactor Coolants
Effects of Post-Processing Variability on Radiation Response of Additively-Manufactured HT9
Enabling In-situ Crack Growth Testing and Monitoring in VTR Cartridge Loop Environments
Explaining the Corrosion Morphology of Structural Materials in Molten Fluoride Salts With/Without Radiation
Fundamental In-situ Experiments Coupled to High-throughput Approaches to Understand Radiation Damage in FCC and BCC Compositionally Complex Alloys
In situ Crack Loading and Measurement Techniques for Gen IV Reactor Coolant Media
In Situ Observation of Irradiation Damage in Polycrystalline Nuclear Graphite
Investigation of Uranium Silicide Fuel Form Additions through Rietveld Refinement and Internal Standard P-XRD
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Modified stereo TEM for 3D analysis of defects
Nanomechanical Change of Tungsten in ELM Conditions
Nonlinear Ultrasound for Nondestructive Evaluation of Microstructural Defects
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