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Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Interrelated Extremes in Materials Degradation for Fission and Fusion Environments
Presentation Title Review of Point Defect Structures in Hexagonal Close Packed Metals and Across the Periodic Table
Author(s) Andrew Ralph Warwick, Pui-Wai Ma, Sergei Lvovich Dudarev
On-Site Speaker (Planned) Andrew Ralph Warwick
Abstract Scope Fission and fusion reactors often use lightly alloyed bcc, fcc and hcp metals. Neutron irradiation generates vacancies and self-interstitial atoms, whose relaxation volume tensors are key to modeling radiation-induced stress and deformation. We extend prior defect studies in bcc [1] and fcc [2] metals by presenting an ab-initio dataset containing relaxation volume tensors of intrinsic point defect across 16 hcp metals [3]. This spans nearly all technologically relevant close-packed metals, excluding lanthanides and actinides. We find vacancy and interstitial relaxation volumes are on average −35% and +146% of the metal’s atomic volume, respectively. This database supports the development of machine learning potentials and enhances predictive models for radiation effects in fission and fusion environments. [1] P.-W. Ma et al., Phys. Rev. Mater. 3, 013605 (2019). [2] P.-W. Ma et al., Phys. Rev. Mater. 5, 13601 (2021). [3] A.R. Warwick et al., arXiv:2505.19341 (2025).
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Computational Materials Science & Engineering,

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Accelerating Nuclear Materials Development Through Thermal Gradient Ion Irradiations
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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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