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Meeting 2027 TMS Annual Meeting & Exhibition
Symposium Spectroscopic Methods and Analysis for Nuclear Energy Related Materials
Presentation Title Irradiation-damage Response of Stable Grain-boundary-decorated Nanocrystalline Multi-principal-element Alloy
Author(s) Ahmed Alade Tiamiyu
On-Site Speaker (Planned) Ahmed Alade Tiamiyu
Abstract Scope While Nanocrystalline (NC) materials constitute a high density of grain-boundaries (GBs) that act as irradiation-induced defect sinks, they are susceptible to grain growth at low-temperatures, negating their potential benefits in nuclear applications. Here, the effect of prior thermodynamic GB decoration, aimed at suppressing grain growth, on the irradiation-damage response of a model multi-principal-element alloy (MPEA) is studied and compared with that of an undecorated counterpart. Using the Intermediate Voltage Electron Microscopy (IVEM)-Tandem facility at Argonne National Laboratory, for in situ experiments in a transmission electron microscope (TEM) under heavy-ion irradiation with 1 MeV Kr2+ ions at room-temperature, and post-irradiation characterization by synchrotron X-ray diffraction and scanning/TEM, we found that prior GB-decoration significantly suppresses defect formation and mitigates irradiation-induced grain growth compared to undecorated MPEA and those in literature. This talk will also cover a new mechanism for suppressing irradiation-induced defect formation—spatial restriction effect (grain refinement below a critical threshold).
Proceedings Inclusion? Planned:
Keywords High-Entropy Alloys, Nanotechnology, Powder Materials

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advancing Neutron Scattering Techniques for Nuclear Materials
Application of Synchrotron X-ray Absorption Spectroscopy to Nuclear Materials
Characterizing Nuclear Energy Related Materials with Laser Ablation Laser Ionization (LALI) Mass Spectrometry
Chemical bonding in UO3 polymorphs: a QTAIM–Hessian-matrix perspective on short U–O and oxo bonds
Determination of High Temperature Mechanical Properties of Nuclear Fuel Using Temperature Resonant Ultrasound Spectroscopy
High temperature Raman spectroscopy of in-situ annealing of ion irradiated SiC and residual stresses in SiC/SiC composites
In-situ Raman Spectrometry of Passive Surface Layers on Stainless Steel
In-Situ UV–Vis Quantification of Chlorobasicity in Binary Molten Chlorides: A Spectroscopic Framework for Molten Salt Reactor Chemistry
Irradiation-damage Response of Stable Grain-boundary-decorated Nanocrystalline Multi-principal-element Alloy
Linking Atomic Structure to Engineering Performance in Refractory Materials for Fusion and Fission
Multimodal chemical imaging and microanalysis of intermetallic materials
NMR Spectroscopy of Zirconium Carbides after High-Temperature Hydrogen Exposure
Nuclear Materials Research using the Activated Materials Laboratory and the Advanced Photon Source
One dislocation, one pore at a time: Probing radiation damage in nuclear materials
Potential of atom probe tomography for mapping hydrogen isotopes in nuclear materials
Raman Spectroscopy of Lanthanides in LiCl-KCl Eutectic for Nuclear Energy Systems
Real-Time Spectroscopic Characterization of Molten Salt Systems Using Electrochemical–LIBS Data Fusion and Probabilistic Neural Networks
Surface-Sensitive X-ray Absorption Spectroscopy for Investigating Corrosion Mechanisms in Actinide Metals
Synchrotron-based high-{energy/temperature/strain/modality} characterization resources for nuclear materials research at NSLS-II
Three-Dimensional Characterization of Crack and Inclusion Networks in a Service-Exposed Baffle Former Bolt Using High-Energy X-Ray Microscopy
Understanding Temperature in Extreme Conditions

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