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Meeting 2025 TMS Annual Meeting & Exhibition
Symposium Spectroscopic Methods and Analysis for Nuclear Energy Related Materials
Presentation Title Studying the use of x-ray line profile analysis in irradiated materials via atomistic simulations
Author(s) Chris Race, Melvyn Larranaga, Tamas Ungar, Philipp Frankel, Jake Larkin
On-Site Speaker (Planned) Chris Race
Abstract Scope The zirconium alloys used in nuclear fission reactors undergo irradiation-induced growth (IIG), an anisotropic shape change resulting in the lengthening of the fuel rods. This is a result of the formation of dislocation loops and so improved understanding of IIG requires quantification of loops in irradiated zirconium alloys. One approach is direct counting in a transmission electron microscope, but this is time consuming, resulting in poor statistics. An alternative is to infer loop content from peak shape changes in an x-ray line profile. We employ atomistic computer models of populations of dislocation loops, together with line profiles calculated from those models, to probe the dependence of the line profile on details of the defects present. We uncover trends in the peak shape that correlate with features of the loop populations, offering a systematic way to improve and validate line profile analysis in the characterisation of irradiated material.
Proceedings Inclusion? Planned:
Keywords Modeling and Simulation, Characterization, Nuclear Materials

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advanced synchrotron characterization techniques for fusion materials science
Atomic-scale structural analysis of metastable zirconia
Complementarity of Neutrons and Positrons in Assessing Material Damage for Nuclear Applications
Correlative Investigation of Hydride Phase Formation and Transformation in Zircaloy-4 Using In Operando XRD and Feature Relocation EBSD-SEM
Correlative multi-modal analysis of nuclear graphite deformation mechanisms
Examination of U19Pu10Zr fluff structure by X-ray tomography and time-of-flight secondary ion mass spectrometry
In-situ Synchrotron Diffraction Investigations of a Scalable, Non-equilibrium Processing Route of ODS Steels for Nuclear Power
In situ helium implantation and Rutherford backscattering analysis of helium retention in amorphous SiOC
Investigating nuclear materials via laser based and positron annihilation spectroscopy techniques to understand their performance
Investigation of Local Defects in Ln-doped UO2: Impact of Fabrication Condition and Lanthanide type
Nano-scale Orientation Mapping Using Electron Backscatter Diffraction
Nanostructural Characterization of Electron Beam Welded Reactor Pressure Vessel Steel via XANES and Nano-CT
Nuclear Materials Research at the Synchrotron
Observing radiation enhanced diffusion in model Fe-Cr alloys and their oxides using atom probe tomography
Quantification of total irradiation damage in nuclear graphite using Raman spectroscopy
Revealing the Crystal Chemistry and Dissolution Kinetics of Doped Uranium Dioxide Nuclear Fuel
Studying the use of x-ray line profile analysis in irradiated materials via atomistic simulations
Synchrotron Characterization of Uranium Boride Alloyed with Chromium Oxidation Behavior
The Surprising Beneficial Effect of Low-Dose Proton Radiation on Suppressing the Corrosion Reactivity of Thermally Oxidized Iron
The use of spatially resolved EELS spectroscopy to elucidate irradiation induced phase transformation in Fe2O3 and Cr2O3 irradiated with ions and its impact on irradiation induced-loop formation
ToF-SIMS Characterization of Irradiated U-Zr FCCI Region Using Spectra Clustering
Vapor analysis by combination spectroscopy in a novel optical cell
X-Ray Diffraction-Computed Tomography (XRD-CT) Facility at NSLS-II for Studying Materials for Nuclear Applications

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