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Meeting MS&T23: Materials Science & Technology
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments IV
Presentation Title Transition Metal Carbonitride Materials Exposed to Swift Heavy Ions
Author(s) Jacob Minnette, Evan Williams, Donald Chaney, Eric O'Quinn, William Cureton, Matthew Kurley, Changyong Park, Christina Trautmann, Maik Lang
On-Site Speaker (Planned) Jacob Minnette
Abstract Scope Transition metal carbonitrides are of significant interest for nuclear energy research for numerous applications, including as a surrogate for advanced fuel forms. In this study, the effect of swift heavy ion irradiation on transition metal carbonitrides (ZrCxN1-x & HfCxN1-x) was investigated. Following irradiation with 198 MeV Xe ions and 946 MeV Au ions, samples were characterized with synchrotron X-ray diffraction and X-ray absorption spectroscopy. The major radiation response was a unit-cell expansion mechanism that proceeded (i) through a direct-impact process saturating at a fluence of ~8x1011 ions/cm2 followed by (ii) a linear increase with no apparent saturation up to 6x1013 ions/cm2. The two-step swelling stands in contrast to the behavior of CeO2 or ThO2 irradiated under identical conditions. The two-step mechanism was independently observed for both carbonitride materials and irradiation conditions, and the overall swelling was higher for the 198 MeV Xe irradiation, correlated with the higher imparted energy density.


Accelerated Assessment of Microstructure-Mechanical Property Relationships in Ni Based Superalloys
Accelerated Creep Testing for High-Temperature and Nuclear Applications
Advanced In-situ Strain Mapping for Zr Oxidation by 4D-STEM
Assessing the Ability of Nuclear Fuel Performance Codes to Predict Radially Resolved Properties in Oxide Fuels
Capturing 3D Evolution of Twin Networks in Titanium as a Function of Applied Strain
Effect of Solutes on the Radiation Induced Segregation in Ferritic Alloys at ∑3- grain Boundaries
Effect of Strain Rate on Tensile Properties of C250 Maraging Steel
Enabling Multiscale Materials Characterization with Machine Learning
Four-dimensional Scanning Transmission Electron Microscopy (4D-STEM) Characterization of Intergranular Corrosion of Austenitic Stainless Steels in Lead-bismuth Eutectic
High-Temperature Irradiation Behavior of Piezoelectric Aluminum Nitride
In Situ SEM Nanomechanics at Cryogenic Temperatures
Interdiffusion Behaviour of UN with Zircaloy-4 via Diffusion Couple Studies
M-1: Novel Method for Fabricating and Analysis of 3D Printed Composite for Radiation Shielding Containing Metalized Halloysite Nanotube
Mapping Elemental Distributions Across Thin Corrosion Films Formed on Nuclear Reactor Core and Structural Materials via Ex-situ And In-situ Atom Probe Tomography
Multimodal Characterization of Materials Corrosion in Molten Salts
Phase Stability of Delta-ZrH Under Ion Irradiation
Probing Nanoscale Properties of Radioactive Material by Advanced Correlative Microscopy
STEM-based Mapping of Nanoscale Point Defects Produced via Temperature, Irradiation, And Corrosion
Structural Stability of REE-PO4 (REE=Sm,Tb) under Swift Heavy Ion Irradiation
Thermodynamic Modeling and Calculation of Phase Formation Processes Under Irradiation Conditions of Uranium-plutonium Nitride Fuel
Transition Metal Carbonitride Materials Exposed to Swift Heavy Ions

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