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Meeting 2025 TMS Annual Meeting & Exhibition
Symposium Meeting Materials Challenges for the Future of Fusion Energy
Sponsorship TMS Structural Materials Division
TMS: Nuclear Materials Committee
TMS: Additive Manufacturing Committee
TMS: Mechanical Behavior of Materials Committee
Organizer(s) Tianyi Chen, Oregon State University
Amy Gandy, United Kingdom Atomic Energy Authority
Reuben Holmes, Kyoto Fusioneering
Ian Mccue, Northwestern University
Sneha Prabha Narra, Carnegie Mellon University
Jason Trelewicz, Stony Brook University
Weicheng Zhong, Oak Ridge National Laboratory
Scope With the establishment of the Bold Decadal Vision for Commercial Fusion Energy, scientific and technical innovations materials have been thrust to the forefront of the critical needs if the community is to succeed along this ambitious timeline toward carbon-free energy production. The fusion environment inevitably exposes materials to high heat, neutron, and particle wall loading that collectively induce damage in plasma facing, structural, and blanket materials, ultimately limiting their operational lifetimes. A fundamental understanding of the synergy between plasma, neutron, and thermal loads under fusion-relevant conditions, and its implications for materials stability and performance, are key scientific drivers for future innovations in fusion materials.

This is the second iteration of the symposium on Materials Systems for the Future of Fusion Energy, which was first held at the TMS 2022 Annual Meeting & Exhibition. This symposium aims to broadly discuss fusion materials research and the fundamental physics of materials degradation under elevated temperatures, transient heat loads, stresses, irradiation, plasma exposure, and oxidizing environments. Talks are solicited that cover new structural and functional materials systems, fusion specific applications of materials, fundamentals of environmental damage, novel characterization and testing approaches, and advances in modeling and theory for fusion materials.

Topics of interest include, but are not limited to:
• Plasma-facing and structural materials, but findings using novel model material analogues for fundamental mechanism exploration are also of interest.
• Functional materials, particularly the development and characterization of breeder materials, neutron multipliers, coatings and barriers, magnetic materials, and auxiliary system materials.
• The effects of irradiation and environmental damage typical of, or extrapolatable to, conditions encountered in nuclear fusion.
• The influence of transmutation products on microstructure evolution and thermo-mechanical property degradation.
• Tritium retention and interaction with materials.
• Multiscale modeling and simulation of fusion phenomena and material interactions, such as in the processes of plasma contamination and erosion.
• Consideration of off-normal events and associated safety hazards such as the aggressive thermal oxidation and decomposition of plasma facing components in case of air ingress accidents.
• Advanced manufacturing methods that enable scalable, cost-effective fabrication of fusion reactor components, including but not limited to novel powder metallurgy, additive manufacturing, solid state processing, simulations-informed alloy design and processing, etc.

Abstracts Due 07/15/2024
Proceedings Plan Planned:
PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE

A Carbon Foam to SiC Conversion Technology for Flow Channel Inserts
A machine learned potential for H behavior in dispersion-strengthened W
Additive Manufacturing via Directed Energy Deposition of WTaCrV and WTaHfCrV Refractory High Entropy Alloys for Plasma Facing Components
Advancing the Scalable Fabrication of Oxide Dispersion Strengthened (ODS) Steel Plates
Annealing of neutron irradiated tungsten to assess the stability of irradiation induced transmutant solute clusters
Assessment of additive manufacturing techniques for obtaining Ferritic/Martensitic ODS
Benchmark Study of Three-Element Medium Entropy Alloy WTaV for Fusion Reactors Plasma-Facing Applications
Characterisation of Oxide Dispersion Strengthened steels for nuclear fusion application
Current R&Ds on Advanced Breeding Functional Materials for JA DEMO activities
Defect phase diagrams and structure-property relationships for screw dislocations of tungsten in the presence of hydrogen studied by atomistic simulations
Demystify Radiation-Enhanced Hydrogen Isotope Diffusion
Design Strategy of PWHT-Free Reduced-Activation Bainitic Steel for Vacuum Vessel Components in Fusion Reactors
Development of industrially scalable high-temperature steels for fusion applications
Development of Machine Learned Interatomic Potentials for Modeling Transmutation Products in Fusion First Wall Materials
Development of machine learning potential to study tritium behavior in V-alloy blanket with liquid lithium breeder
Development of SiC Composite Blanket for Fusion
Effect of transmutation products on point defect energies in tungsten from first-principles and machine learning
Effects of ion irradiation on microstructure and micromechanical properties of a ductile-phase-toughened tungsten heavy alloy
Emerging Alloy Materials for Fusion Power
Enhanced radiation resistance of W-based HEA under helium-ion irradiation conditions
Evolution of He bubble morphology during in situ heating of plasma exposed tungsten and tungsten alloys
Exploration of Ferrous Alloys as Radiation Damage Resistant Materials for Fusion
First principles calculations of fusion-relevant transmutation defects in SiC
Fracture Toughness of F82H Steel after Neutron Irradiation to ~70 dpa at 400°C and 500°C
Functional Coating Development for Fusion Reactors
Hierarchical multiscale modeling framework to predict surface morphology of plasma facing components
High Throughput Self-Ion Irradiation and Characterization of Pure Tungsten
Identification of transmutation products in irradiated tungsten
Impact Dynamics of High-Velocity Tungsten Dust in Fusion Reactors: A Molecular Dynamics Study
Impact of Soret effect on hydrogen and helium retention in PFC tungsten under ELM-like conditions
Improved damage detection around grain boundaries in tungsten from atomistic calculations
In situ micropillar compression study of ultra-fine-grained Tungsten at elevated temperature
Innovative Lithium-Based Tritium Breeder Material with Promising Microstructure
Investigation of microstructure and mechanical properties in cost-effective thermomechanically processed nanostructured ferritic alloys
Irradiation experiments for fusion blanket materials
Laser Additive Manufacturing of PFCs for Nuclear Fusion: Studying the Influence of Tungsten Deposition on RAFM Steel Using Multimodal Synchrotron Imaging
Love & Marriage: point defect coexistence in nanostructured tungsten
Material characterization of lateral transmutation gas gradients in triple-ion irradiated F82H-IEA
Micromechanical investigation of WC for shielding applications in compact fusion devices
Microstructural changes in ion and neutron irradiated REBCO-based magnet materials for Fusion.
Microstructure Modification of Tungsten by Alloying, Dispersion Strengthening, and Thermomechanical Processing for Fusion Energy Applications
Modeling of Dislocation Loop Evolution in Iron through Kinetic Monte Carlo
Phase Field Fracture Modeling to Investigate the Integrity of Lithium Aluminate Pellets Used for Tritium Breeding
Physics-based evaluation of general fusion facility concepts for a prototypical neutron fusion source
Predicting high-dose irradiation damage using statistical surrogate models of cascade defect production
Processing and irradiation damage in Novel tritium breeding ceramics with high lithium content
Progress and issues of R&D on fusion DEMO structural materials in Japan
Radiation effects challenges in high-performance materials
RAFM Welding with In-Situ Thermal Processing for Simplified First Wall Fabrication
Refractory Alloy Processing Challenges for Next-Generation Energy Systems
Responses of dispersion-strengthened tungsten to high heat flux and high fluence helium irradiation
Scale-Up of Advanced Castable Nanostructured Alloys for Fusion First-Wall/Blanket Applications
Shrinking Pains – Materials Challenges in a More Compact Fusion Device
Simulating plasma-surface interactions with deuterium beams experiments: effect of tungsten oxidation
Spark Plasma Sintering of Dispersion-Strengthened Tungsten for Fusion Applications
Synergetic Effects of Hydrogen on Cavity Formation in Candidate Fusion Blanket Materials: Past and Future Studies
Synergistic Study of Neutron Irradiation and Hydrogen Exposure on Tungsten
Temperature dependent thermal-mechanical properties of plasma-facing materials - W, SiC, and Fe-Cr alloy
The effect of ion irradiation conditions on the damage morphology of a tungsten heavy alloy
The role of AI in advancing materials development and testing for fusion energy deployment
The Role of Hydrogen Co-Injection on the Cavity Microstructure of Triple Ion Irradiated F82H-IEA
Thermal permeation of tungsten wafers
Thermomechanical Processing of Tungsten and its Alloys for Fusion Energy Applications
Toward understanding of the response of SiC to fusion neutron irradiation
Transmutations in advanced nuclear ceramics exposed to fusion environments
Tungsten-based WTaVCr refractory high entropy alloys for fusion energy applications
Tungsten Boride Shielding Material for Fusion Reactors
Ultra High Temperature Ceramics for Fusion Energy applications.
Understanding the role of short-range order on defect thermodynamics in tungsten alloys
W-Cr Composite with Improved Fracture Toughness for Plasma-Facing Material: Fabrication and Mechanical Properties Characterization


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