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Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Special Topics in Nuclear Materials: Reproducibility and Uncertainty; Hydrogen Effects; Space and Microreactor Systems
Presentation Title X-Ray Absorption Signatures of Plutonium Alloys Accounting for Composition, Age, and Mechanical Stress
Author(s) Benjamin Walusiak, Alice Iulia Smith, Arjen van Veelen, Paul H. Tobash, Najeb Mohammed Abdul-Jabbar
On-Site Speaker (Planned) Benjamin Walusiak
Abstract Scope Phase transformations within Pu and its alloys have long been a focus of study due to their complicated phase behavior. Being radioactive in nature, Pu and its alloys are subjected to continuous self-irradiation that results in lattice damage, void swelling, He bubble accumulation and α-decay products (Am, U, and Np). X-ray absorption spectroscopy (XANES, EXAFS, etc.) has proven viable for characterizing a wide range of local structural effects in general, including those in Pu alloys. Pu alloys have been analyzed via EXAFS, using the Pu LIII edge, Ga K edge, or Fe K edge to evaluate the local structural environment of these elements as a function of age, alloy composition, or application of mechanical stress. Elemental maps of these alloys have been collected to provide additional insight into synthesis, processing, and sample history. LA-UR-25-26594
Proceedings Inclusion? Planned:
Keywords Nuclear Materials,

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Assessment of Hydrogen Diffusion in Vanadium for FLiBe Blanket Designs
Characterization of the Impact of Transmutation Gases on Deformation Mechanisms of Spallation Neutron Source Component Materials
Characterization of Zirconiumhydride Decomposition by Neutron Diffraction and Modeling
Degradation of Yttrium and Zirconium Hydrides Under Irradiation in the MIT Reactor
Deleterious Effect of Electrical Discharge Machining Interaction Layer on Metallic Zirconium Hydride Conversion Process
Density Functional Theory Analysis of Candidate Tritium Permeation Barriers for Vanadium Alloys as a Fusion Structural Material
Effect of Radiation Damage on Hydrogen Equilibrium Vapor Pressure over Irradiated Zircaloy-4
Effect of Sulfide Corrosion on the Interatomic Spacing of Copper Measured by Synchrotron HEXRD
Evaluating Measurement Consistency in Irradiated Stainless Steel Using Complementary Microscopy and Spectroscopy Techniques
Hydrogen Isotope Retention in Displacement Damaged Tungsten
Hydrogen Retention in Neutron-Irradiated Tungsten and Tungsten-Rhenium Alloys
Hydrogen Retention in Zirconium Hydride Moderator: Atomistic Insights Into the Role of Microstructural Defect Sinks
Insights From Post-Irradiation Examination of Yttrium Hydride at ORNL and INL
Insights Into Radiation-Induced Ductility Enhancement of Inconel 718 Using In-Situ SEM-EBSD Tensile Testing
Irradiation Damaging EUROFER97 to High Dose at Different Temperatures
Irradiation Effects on Optical Fiber Sensors and Measurements
K-10: In-Situ TEM Study of Gamma Hydride Behavior During Thermal Cycling in Zircaloy-4: Transformation Kinetics, Mechanisms, and Sample Preparation Effects
K-8: Deuterium Retention in Grain Oriented, Additive Manufactured Tungsten
K-9: Effect of Electrolytic Hydrogen Charging on the Lattice Parameter of Copper Measured by Synchrotron HEXRD
Mechanism of Helium-Assisted Hydrogen Retention in Ferritic-Martensitic Steels Under Irradiation
Molten Metallic Nuclear Fuel Containment: Challenges and Implications for Space Power and Propulsion
Neutron Irradiation Effects on Lithium Aluminate Pellets With Different Thickness
Phase Stability and Hydrogen Diffusion in Irradiated Yttrium Hydride
Post Irradiation Examination of an Irradiated 6061-T6 Aluminum Proton Beam Window
Quantifying and Reducing the Errors in Void Swelling Calculations of Irradiated Materials With Transmission Electron Microscopy
Replicating In-Service Hydriding of Zirconium Alloy Fuel Claddings Utilizing a Combined Experimental-Computational Approach
Revisiting He Bubble Measurements in Aged Pu Using Modern S/TEM Techniques
Sensitivities and Uncertainties in HFIR Materials Irradiation Experiments
Spatial Characterization of Hydrogen in Nuclear Materials
Thermal Gradient Effect on Defects Transport in Tungsten
Thermophysical Properties of Irradiated Yttrium Hydride Moderator Material
Toward Rapid Emulation of Neutron Damage With Ions: Helium Effects on Microstructural Evolution in Ion-Irradiated Historic Heats of V-4Cr-4Ti Alloy (US832665, US832864)
Understanding the Role of Hydrides in the Oxidation Behavior of Zircaloy-4
Using Thermo-Chemistry Modeling to Inform Metal Hydride and High Temperature Fuel Design, Operation, and Safety
X-Ray Absorption Signatures of Plutonium Alloys Accounting for Composition, Age, and Mechanical Stress
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