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Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Interrelated Extremes in Materials Degradation for Fission and Fusion Environments
Presentation Title Dislocation effects on high temperature He embrittlement in iron-based alloys
Author(s) Zehui Qi, Miguel L. Crespillo, Steven John Zinkle
On-Site Speaker (Planned) Zehui Qi
Abstract Scope For fusion reactor and Gen IV reactor concepts, the higher operating temperatures and radiation doses represent new materials challenges. High-temperature helium embrittlement (HTHE) may be one mechanism that limits the lifetime of potential structural materials. Previous in-situ creep tests have shown that tensile stress can significantly enhance HTHE. However, our observations suggest that elastic stress alone, without a threshold dislocation density, does not induce noticeable stress-enhanced HTHE effects. In this study, 316L stainless steel and Fe-9%Cr alloys with varying pre-existing dislocation densities were helium-implanted to a peak concentration of ~1800 appm, both with and without an initial elastic stress of ~100 MPa at 750 °C. The size and number density of cavities (both in the matrix and at grain boundaries) were characterized by TEM to investigate cavity behavior in relation to applied stress and dislocation density. The results indicate that plastic deformation (dislocations) plays an important role in HTHE.
Proceedings Inclusion? Planned:

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Accelerating Nuclear Materials Development Through Thermal Gradient Ion Irradiations
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Atomic-scale characterisation of the in-pile corrosion of ZIRLO and X2 Zr cladding alloys
Combined experimental, simulation and computer vision analysis of irradiated microstructure
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
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
Integrating high-throughput ex-situ, and in-situ, corrosion testing to investigate irradiation effects on molten salt corrosion
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
Large-scale finite element models informed by neutron transport and atomistic simulations
Mechanistic understanding of irradiation damage in fuel assemblies: an overview of the MIDAS research programme
Predicting Fracture Toughness Degradation in Irradiated Duplex Structure Stainless Steels Using Data-Driven Methods
Revealing deformation behaviour of tungsten-copper composites for fusion applications
Review of point defect structures in hexagonal close packed metals and across the Periodic Table
Self-ion irradiation induced defect evolution and micromechanical response of W
Simultaneous Irradiation and Corrosion in High Temperature Coolants - The Plot Thickens
Simultaneous or Sequential? Evaluating irradiation-corrosion approaches for Molten Salt Reactor materials
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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