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Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Interrelated Extremes in Materials Degradation for Fission and Fusion Environments
Presentation Title He Ion Irradiation Induced Defect Evolution and Micromechanical Response of W
Author(s) Adil Wazeer, Yinghang Liu, Chang Xia, Ke Xu, Debargha Paul, Vaibhav Singh, Yongqiang Wang, Matthew Ryan Chancey, Tim Graening, Xiao-Ying Yu, Haiyan Wang, Xinghang Zhang
On-Site Speaker (Planned) Adil Wazeer
Abstract Scope Understanding radiation tolerance and high-temperature performance of tungsten (W) is critical for its deployment in nuclear fusion environments, where intense helium (He) implantation from the plasma significantly alters near-surface microstructure. In this study, pure W was subjected to He ion irradiation at elevated temperature to simulate reactor-relevant helium exposure conditions. TEM investigations revealed pronounced defect evolution with increasing fluence, including the nucleation and growth of He bubble and bubble coalescence. The presence of helium-stabilized vacancy clusters led to distinct microstructural features compared to displacement-dominated irradiation, highlighting the strong role of He–defect interactions. To evaluate the mechanical implications of helium-induced damage, in-situ SEM micropillar compression tests were performed on both He-irradiated pillars. The results demonstrate significant changes in deformation behavior and altered strain localization, governed by bubble-dislocation interactions and thermal activation processes.
Proceedings Inclusion? Planned:
Keywords Characterization, Nuclear Materials,

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Accelerating Nuclear Materials Development Through Thermal Gradient Ion Irradiations
Analysis of Attenuation Data From the Beltline of the Reactor Pressure Vessel From the Decommissioned ZION 1 Nuclear Power Plant
Assessment of Brittle Fracture of 304L Austenitic Stainless Steel – Material of Light Water Reactor Core Internals
Design Kinetic Parameters for Improved Resilience of Materials Under Irradiation
Detailed Post-Irradiation Examination of Harvested PWR Baffle-Former Bolts
Developing Dispersion-Strengthened Tungsten to Withstand Coupled Extremes in Fusion Reactors
Development of In-Situ Irradiation Creep Testing and Application to a Ferritic-Martensitic Steel
Dislocation Effects on High Temperature He Embrittlement in Iron-Based Alloys
Disordering and Defect Evolution Processes at Epitaxial Fe3O4 / Cr2O3 and Fe2O3 / Cr2O3 Interfaces Under Irradiation
Evaluation of SiC-Based Composite Tubes Under Multi-Physics Environments for Accident-Tolerant Cladding Development
Ghosts in the Mechanism: Corrosion Happening at the Same Time as Other Stuff
He Ion Irradiation Induced Defect Evolution and Micromechanical Response of W
High-Throughput Synchrotron Methods for Fusion Materials Research
Impact of Oxidation Temperatures and Different Helium Irradiation Doses-Induced Defects in Fe-18Cr
Integrated Model of Grain Growth in Tungsten Armor Materials Under ARC Plasma Edge Operation Conditions
Interphase Characterisation and Testing on SiC-Based CMCs for Fusion Applications
Investigating the Effect of High-Temperature Ion Irradiation on the Microstructures and Mechanical Properties of (Cr,Hf,Ta,Ti,Zr)C and (Hf,Ta,Ti,W,Zr)C Compositionally Complex Carbides
Investigation of Neutron Irradiation Effects on T91 Ferritic/Martensitic Steel for Fusion Reactor Applications
Irradiation Temperature and Mechanical Properties in Neutron Irradiated Ferritic Steel
Predicting Fracture Toughness Degradation in Irradiated Duplex Structure Stainless Steels Using Data-Driven Methods
Review of Point Defect Structures in Hexagonal Close Packed Metals and Across the Periodic Table
Simulated Ex-Service SFR Fuel Cladding for Characterization of Degradation Under DGR Groundwater Conditions
Simultaneous Irradiation and Corrosion in High Temperature Coolants - The Plot Thickens
Study on Corrosion Properties of F82H/SUS316L Dissimilar Joints Produced by Fiber Laser Welding or Friction Stir Welding
Three Dimensional Characterization of the Microstructures of PWR Baffle Former Bolts After 40 Years in Service
Transmission Electron Microscopy of Second Phase Precipitates in Zirconium Alloys Exposed to Neutron Irradiation in the Advanced Test Reactor
Understanding Coupled Environments Radiation +
Understanding Synergistic Degradation Mechanisms in Nuclear Materials Through Coupled Environment Testing
Vessel Material Selection and Design for the ARC Fusion Power Plant

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