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Meeting 2020 TMS Annual Meeting & Exhibition
Symposium Accelerated Materials Evaluation for Nuclear Applications Utilizing Irradiation and Integrated Modeling
Presentation Title Recent Applications of Ex-situ Transient Grating Spectroscopy to the Study of Radiation-induced Degradation of Nuclear Materials
Author(s) Sara Elizabeth Ferry, Cody Dennett , Angus Wylie, Pär Olsson, Michael Short
On-Site Speaker (Planned) Sara Elizabeth Ferry
Abstract Scope Transient grating spectroscopy (TGS) is a non-contact, non-destructive optical heterodyne detection technique used to quickly obtain acoustic and thermal transport properties in irradiated materials. TGS is a useful tool for detecting and characterizing radiation damage induced changes in nuclear materials with greater ease and speed than is afforded by traditional post-irradiation examination (PIE) techniques, and can be used both in situ and ex situ. Here, we present recent results from two ongoing ex situ studies. In the first, we expand upon previous work examining irradiation-induced thermal diffusivity changes in single crystal niobium by repeating the experiment with additional metals, and supplementing the experimental results for all tested metals with density functional theory (DFT) studies. In the second, we demonstrate that TGS can be used to detect the onset of “fuzz” development in plasma-exposed polycrystalline tungsten. This radiation damage mode is of particular concern for first-wall materials in fusion devices.
Proceedings Inclusion? Undecided

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

A Comparative Study of Two Nanoindentation Approaches for Assessing Mechanical Properties of Ion-irradiated Stainless Steel 316
A Comparison of Ring Pull and Axial Tensile Tests of HT-9 and 14YWT Thin-walled Tubes
A Virtual Experiment Approach to Positron Annihilation Spectroscopy
Alpha Self-Irradiation of Archive and Irradiated Fast Reactor Fuels
Behaviors of Implanted Xe and Kr Gas Bubbles in CeO2 After Annealing and Rapid Heating Test
Changes in the Starting Microstructures of U-Mo Fuels due to the Effects of Neutron Irradiation
Characterization of Helium Implanted Single Crystal Titanium
Comparison of Radial Microstructural Changes in Fast Reactor MOX Fuels Across Varying Burnup Profiles
Controlling Helium Morphology in Pure Metals: Toward Uniform Samples for the Accelerated Measurement of Bulk Irradiated Properties
Damage Mitigation Strategies for Femtosecond Laser Machining of Micro-tensile Bars
Defect Evolution and Radiation Resistance of Advanced Fusion Materials Under Heavy Ion and Low Energy Helium Irradiation
Development of Advanced Low N-12Cr (wt.%) Ferritic/Martensitic Steel for Reactor Applications
Diffusion Analysis of Metallic Fission Products in Tristructural-isotropic Coated Fuel Using Representative Diffusion Couples
Diffusion of Fission Products in Virgin Nuclear Graphite
Direct Compaction of Dispersion Fuels Using a Matrix Deposition on the Fuel Particles
Direct Measurement of Radiation Damage Through the Energy Stored in Defects: Simulations and Experiments
Effective Defect Sinks in Metallic Composite with Nanodispersoids: In situ Ion Radiation Transmission Electron Microscopy and Position Annihilation Lifetime Spectroscopy
Effects of Helium Ion Irradiation on Single Crystal Vanadium
Fabrication and Characterization of Massive Crack-free Delta Phase-zirconium Hydride for High-performance Moderator Application
Fabrication of Low-enriched Uranium Dispersion Targets with a High Uranium Density for Mo-99 Production
High-Throughput Synthesis and Ion Irradiation of High-Entropy Alloys using Additive Manufacturing
Impact of Ionization Effects and Defect Trapping on Microstructure Evolution in Light Ion Irradiated Uranium Dioxide
In-situ Heavy Ion Irradiation of FCC and BCC High-entropy Alloys at Cryogenic and High Temperatures
In-situ Neutron Characterization of Advanced Nuclear Fuels - The Road to a New Neutron Irradiation Testing Capability
In-situ Observation of Radiation-induced Phase Transformation in U-Mo
In-situ Studies on the Mechanical Properties of He Ion Irradiated Nanotwinned Ag
Interphase Distribution Behavior of Oxide Nanoparticles Triggered by Isothermal Ferrite Transformation in 9Cr ODS Steels
Irradiation Behavior of Mechanically Processed Zr-Nb Multilayers at Very High Doses
Kinetic Study on the Evolution of Nano-ceramic Coatings Under Heavy Ions Irradiation
Linking Defect Structure and Property Evolution in Ion-irradiated Tungsten: A Multi-facetted View
Mechanical Properties of Ion Irradiated and Helium Implanted HT9 Micropillars
Microstructural and Micro-chemical Characterization of Safety Tested TRISO UCO Fuel Kernels Irradiated in the Advanced Test Reactor
Microstructural Changes and Corrosion of Proton-pre-irradiated Hastelloy N in FLiNaK Molten Salt
Microstructure and Mechanical Behavior of Directed Energy Deposition Laser Additively Manufactured T-91
Microstructure of HT-9 Cladding After fuel-cladding Chemical Interaction with an Annular U-10Zr Fuel Irradiated to 3.3% FIMA
Multiple Scale Mechanical Testing of Neutron Irradiated FeCrAl Alloys
Neutron Irradiation Damage and Fission Product Transport in the SiC Layer of TRISO Fuel Particles
On a Theory Based Accelerated Testing Methodology for Swelling.
On the Role of Heterogeneity in Concentrated Solid‒solution Alloys in Enhancing their Irradiation Resistance
Promotion and Suppression of the G-phase in Steels
Radiation Response of HT9 Ferritic/Martensitic Alloys as a Function of Interstitial Content
Rapid Investigation of Irradiation Temperature Sensitivity Using Charged Particles
Recent Applications of Ex-situ Transient Grating Spectroscopy to the Study of Radiation-induced Degradation of Nuclear Materials
Small Scale Mechanical Testing of Ceramic Interfaces in Nuclear Materials: Characterizing the Impact of Elastic Mismatch on Stress Intensity and Property Extraction
Synthesis of Intermetallic UZr2+x and Its Phase Transformation
Temperature Shift Evaluation for G-phase Clustering in Ferritic-martensitic Alloys
Testing of Nuclear Fuels and Materials in the Advanced Fuels Campaign
Three-dimensional Analysis of the IPyC/SiC Interface in Irradiated TRISO Fuel Particles

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