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Meeting 2027 TMS Annual Meeting & Exhibition
Symposium Transmutation Effects in Materials in Fission, Fusion, and Spallation Environments
Presentation Title Nanoscale distribution of He and H gases in nanocavities of post-irradiated proton beam window
Author(s) Hsin-Yun Chao, Timothy G Lach, Jordan A Hachtel
On-Site Speaker (Planned) Hsin-Yun Chao
Abstract Scope The Inconel 718 proton beam window of the Spallation Neutron Source at Oak Ridge National Laboratory was demonstrated to have an increase in ductility with the increase in irradiation dose through tensile testing. This improvement in ductility is unexpected since beam irradiation generally increases strength but decreases ductility. Therefore, in-depth characterization of the material is necessary to understand its underlying properties. In this work, we investigate the dynamics of He and H gas in nanocavities of Inconel 718 using scanning transmission electron microscopy (STEM) equipped with electron energy loss spectroscopy (EELS) before and after solution annealing from 500 to 900 °C with a 30 min hold at each temperature. Furthermore, non-negative matrix factorization (NMF) is performed on the EELS datasets to analyze spatial features. Results show uniquely varied distributions of He and He gases in the nanocavities as well as cavity size distributions at each temperature range.
Proceedings Inclusion? Planned:
Keywords Characterization, Iron and Steel,

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advances in Oxide Dispersion Strengthened (ODS) Steel Manufacturing for Nuclear Applications
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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