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Meeting 2027 TMS Annual Meeting & Exhibition
Symposium Transmutation Effects in Materials in Fission, Fusion, and Spallation Environments
Presentation Title Effect of stress on grain boundary helium bubble coalescence in iron: An atomistic simulation study
Author(s) Silas John, Li Yang, Brian Wirth
On-Site Speaker (Planned) Silas John
Abstract Scope Molecular dynamics (MD) simulations were used to investigate the coalescence mechanisms of He bubbles at grain boundaries (GBs) in bcc Fe under constant shear stresses at temperatures between 500 K and 923 K. The results show that for temperature, stress above a threshold, bubble migrate along the GB via sliding mechanism. When two bubbles are close to each other, the coupling between GB slide, and asymmetry in GB bubbles positions promotes directional, non-uniform bubble evolution/migration, leading to coalescence. Increasing temperature and stress increases sliding rate, which in turn accelerated bubble coalescence. Notably, deformation is accommodated by coupled GB sliding and migration, with the dominant mechanism strongly influencing bubble coalescence. Specifically, coalescence was observed at Σ5 and Σ13a where sliding dominates but absent in Σ25 and Σ3 where GB migration is the dominant mechanism. In Σ25, GB edge dislocations motion suppress sliding, while high-misorientation Σ3 favors GB migration and inhibits coalescence.
Proceedings Inclusion? Planned:
Keywords High-Temperature Materials, Computational Materials Science & Engineering, Iron and Steel

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

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Automated Cavity Detection for High-Throughput Void Swelling Characterization
Characterization of transmutation products in irradiated 6061-T651 and Inconel 718 proton beam windows
Design of a fission nuclear‑heated PbLi thermal convection loop for fusion blanket testing
Dislocation Mediated HenVm Defect-Complex Diffusion in bcc Fe
Effect of stress on grain boundary helium bubble coalescence in iron: An atomistic simulation study
Effects of Rhenium on Irradiation-Induced Defect Evolution in Tungsten
Effects of Transmutation on Local Ordering and Energetics in Tungsten-Based Plasma-Facing Materials
Effects of transmutation products in Spallation Neutron Source structural alloys
First-principles investigation of H/He synergistic effects in fcc Ni
FLARE: A Tool for Rapid Evaluation of Irradiation Responses for Fusion Materials Design
Gaseous transmutation product softens irradiated Ni-alloy by forming planar complexions
Helium Effects on Microstructural Evolution and Mechanical Properties in Irradiated Reduced Activation Ferritic/Martensitic Steel F82H
High Temperature Helium Embrittlment and Transmutation Gas Driven Damage in baseline and e-beam welds of V-4Cr-4Ti
Imaging transmutational products upon neutron irradiation of structural materials
Influence of Neutron Spectrum on Transmutation Product Evolution in Tungsten Alloys Revealed by Multimodal Synchrotron Characterization
Influence of Rhenium Alloying and Potassium Doping on Hydrogen Isotope Behavior in Neutron-Irradiated Tungsten
Machine Learned Interatomic Potentials for Molecular Dynamics Modeling of Transmutation Products in Fusion First Wall Materials
MECx: A Transferable Surrogate Model for Minimum Energy Configurations in Transmuted Tungsten Alloys
Microstructural and properties evolution of tungsten irradiated with high energy protons and spallation neutrons
Nanoscale distribution of He and H gases in nanocavities of post-irradiated proton beam window
Neutron Energy Spectrum Effects on the Microstructural Evolution of Irradiated Tungsten-Rhenium
Predictive models for irradiation damage in baseline metals: from fundamental atomistic simulations to engineering properties
Radiation Effects in Oxide Dispersion Strengthened Alloys and Implications on Transmutation Gas Management
Radiation effects in reduced activation ferritic-martensitic (RAFM) steel welds for fusion first-wall/blanket applications
Recent Insights into Helium Effects on Cavity Formation in Irradiated BCC Fe–Cr Alloys
Solid and gaseous transmutation effects in irradiated materials
Synthesis and Characterization of Lithium based Compounds for Tritium Breeding Materials for Fusion Energy
The impact of carbon on structure and properties of radiation defects in W and WC.
The Relationship Among Stoichiometry, Microstructural Evolution and Tritium Release in Ternary Lithium Ceramics
Transmutation Effects on Fusion Materials in the ARC Fusion Power Plant and Comparison with Neutron Test Devices
Transmutation Effects on Microstructure and Mechanical Properties of Neutron-Irradiated Tungsten

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