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Meeting 2023 TMS Annual Meeting & Exhibition
Symposium Transmutation Effects in Fusion Reactor Materials: Critical Challenges & Path Forward
Sponsorship TMS Structural Materials Division
TMS: Nuclear Materials Committee
Organizer(s) Arunodaya Bhattacharya, Oak Ridge National Laboratory
Steven J. Zinkle, University of Tennessee
Philip Edmondson, The University Of Manchester
Aurelie Gentils, Université Paris-Saclay
David Sprouster, Stony Brook University
Takashi Nozawa, National Institutes for Quantum and Radiological Science and Technology (QST)
Martin Freer, University of Birmingham
Scope Realization of fusion energy on Earth requires high-performance radiation-tolerant structural and functional materials that can withstand extreme operating conditions envisaged for the fusion first-wall/blanket and plasma-facing components. A major technical gap in the fundamental understanding of fusion-specific radiation damage is due to the high transmutation product generation rates by the fusion neutron spectra, as compared to fission neutrons. Therefore, severe performance degradation due to the synergies between neutron damage and transmutation products is expected for numerous candidate materials for a variety of applications in fusion concepts like the Demonstration Power Plant (DEMO) in EU/Japan or the Fusion Neutron Science Facility (FNSF) in the US. Specific examples include reduced activation ferritic-martensitic (RAFM) steels or oxide dispersion strengthened (ODS) steels for the first-wall/blanket, tungsten alloys for divertor, Cu alloys for high-heat flux components or radio-frequency launchers, SiC/SiC ceramic composites for coolant channels, Li based oxides for solid breeders, to name a few. Until a fusion prototypic neutron source becomes available, grassroot research that can simulate the effect of transmutation products for future validation with 14 MeV neutrons is required using fission neutrons, spallation neutron sources and accelerator based energetic ions.

This symposium is targeting state-of-the-art investigations and technologies on understanding transmutation effects in fusion reactor materials. Investigations involving neutron irradiations, innovative techniques of experimentally simulating transmutation effects and novel facilities to study transmutation related damage situations, especially under the application of thermo-mechanical stresses, are strongly encouraged. This symposium also calls for modelling studies related to transmutation damage and on inventory build-up calculations for future fusion devices.
The topics of interest include the following key aspects, but not limited to:
• Helium and hydrogen effect in first-wall/blanket structural materials (FM steels/FeCr alloys, ODS steels, W alloys, Cu alloys, SiC/SiC): Thermo-mechanical properties degradation
• Transmutation and irradiation damage in tungsten, with specific attention to the effect of Re and Os generation
• Synergistic transmutation and radiation damage in structural and functional non-metals
• Performance degradation of solid breeders by loss of Li due to tritium and helium generation, and including neutron multipliers
• Effect of applied stress on transmutation product migration and clustering
• Modelling of point-defects and transmutation product interactions
• Interaction of transmutation products with microstructural sinks and extended defects
• Evaluation of irradiation spectrum transmutation effects on material behavior in fission, fusion, and spallation neutron environments: novel experiments using existing facilities, inventory build-up calculations.

Abstracts Due 07/17/2022
Proceedings Plan Planned:

Ab Initio and Classical Molecular Dynamics Study of Re Transport in W
Ab Initio Study of Tungsten-based Alloys Under Fusion Power-plant Conditions
Accurate Fe-He Machine Learning Potential for Studying Helium Effects in Ferritic Steels
Advanced Synchrotron Characterization Techniques for Fusion Materials Science
Analysis of Irradiation Damage Accumulation in Bi-phase Tungsten Heavy Alloy Microstructures
Analytical TEM Examination of Re and Os Segregation in Neutron Irradiated Tungsten
Behavior of Helium Cavities in Ion-irradiated Ductile-Phase-Toughened Tungsten
Characterizing Transmutation Products in Materials via STEM and Machine Learning
Co-Segregation of Transmuted Re and Os in Neutron Irradiated Tungsten: First-principles Prediction and Experimental Validation
Critical Evaluation of High Temperature Helium Embrittlement Phenomena in Structural Materials
Discrete and Continuum Models for the Sources of Nonlinear Strain for Macrscopic Simulations of Reactor Components
Effect of Helium on Low-temperature Hardening/Embrittlement (LTHE) in Neutron Irradiated Isotopically Tailored RAFM Steels
Effects of Carbide Dispersoids on Helium Bubble Formation in Dispersion-strengthened Tungsten
Experimental Validation of Simulated Transmutation Predictions for Fusion Materials
Grain-boundary Effects on the Irradiated Damages in W-Re Alloys
He Irradiation of W First-wall Materials: Parameters at Stake for the Bubble Creation, Behaviour and Impact on Tritium Trapping
Helium Effects on Mechanical Properties of (RA)FM Steels
Helium Production in Irradiated Low-temperature Solder Candidates for Novel Fusion Magnet Cables
Impact of Pre-existing Damage on He Irradiated Sintered 3C-SiC
In-situ Helium Bubble Formation and Thermal Evolution in Lithium Metatitanate
Interaction of Hydrogen/Helium with Grain Boundaries and Dislocations in Tungsten
Investigation of High Temperature He Embrittlement Effects in High Performance Nickel-based Alloys
Irradiation Spectrum, Transmutation, and Supporting Materials Use Next Generation Fusion Systems
Machine-learned Interatomic Potential Development for H Trapping in ZrC Strengthened W
Machine Learning Generation of Trajectories for Accurate Modeling Plasma Material Interactions
Magic Numbers on the Shape of Voids Formed by Electron Irradiation in Aluminium
Modeling the Effect of He/dpa Rate on Microstructural Evolution in Ferritic-martensitic Alloys
Modelling of Re/Os Transmutation Product Segregation in Irradiated W Using Atomistic Kinetic Monte Carlo
Molecular Dynamics Simulations of Mixed Materials Effects in Tungsten
No Ball Milling Needed: Revamping Fabrication Route of ODS Steel Plate with Cold Spray and Friction Stir Processing
O-16: Microstructural Investigation of Irradiated REBCO Coated Conductors for Future HTS Fusion Magnets and Other High-dose Environments
Optimization of Tritium Breeding in Molten Salt Blankets: Materials and Geometries
Stability of a Li2TiO3 Candidate Solid-breeder Material Following Li Transmutation
Studies on Transmutation Effects in Reduced Activation Ferritic/Martensitic Steels in Japan
Suppression of Rhenium and Osmium Production in Tungsten-based Materials for Fusion Energy
Synergistic Effects between Radiation Damage and H/He Co-Injection on Swelling in Candidate Fusion Structural Materials
The Effect of Chemical Element Inventory Evolution on Recoil Production and Its Effect on Defect Cluster Evolution in Tungsten
The Effect of Helium on Cavity Swelling in Dual-ion Irradiated Fe and Fe-10Cr Ferritic Alloys
The Effects of High-dose He and H Ion Implantation on the Microstructural Development in EUROFER-ODS Steel
Thermonuclear Fusion: Some Open Issues Concerning Tritium
Tracking Neutron-irradiation Induced Transmutation Using Atom Probe Tomography and Neutron Inventory Calculations
Transmutation Effects in Fine Grained Tungsten: Gas Behavior and the Role of Grain Boundaries
Ultrafast Measurement of Microscopic Energy Flow in He-implanted W

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