21st International Conference on Fusion Reactor Materials

The conference covers all scientific, technological development, and other technical aspects from fundamental materials science to engineering materials.

• Development and qualification of structural materials for DEMO and beyond.
   
  • Ferritic/martensitic steels
  • Advanced and ODS steels
  • Ceramics, ceramic composites, and other low-Z materials
  • Tungsten, refractory alloys, and other high-Z materials
  • Novel highly radiation-resistant alloys
• Materials for high heat flux plasmas facing components: divertor, limiter, first wall.
  • Plasma-facing materials
  • High heat-flux materials: heat-sink and structural application
  • Materials for limiters
  • Liquid metal divertors: material issues
• Development and characterization of functional materials applied in blankets and other n-irradiation affected systems.
  • Breeding and neutron multiplier ceramic materials.
  • Coatings
  • Barriers, insulating materials and flow-channel inserts
  • Plasma-diagnostic system materials
  • First mirrors and auxiliary systems
  • Magnetic materials
• Fusion-specific applications of materials, including environmental effects.
  • Tritium and deuterium: retention, accumulation, diffusion and release, including effects of irradiation
  • Concomitant hydrogen and helium embrittlement
  • Liquid metal embrittlement
  • Irradiation and coolant accelerated crack extension
  • Chemical compatibility: oxidation, corrosion, and environmental effects
• Materials engineering and application including joining of (similar or dissimilar) materials.
  • Fabrication and materials engineering
  • Joining of similar and dissimilar materials: process optimization, properties and development of characterization methods
  • TBM: material issues and technologies
  • ITER material technologies open issues
• Qualification of irradiation effects in neutron sources, accelerators and other test systems including advanced characterization methods.
  • Intense fusion neutron sources for materials validation (DONES and IFMIF-like)
  • Approaches to best estimate irradiated materials engineering data combining databases and modeling ITER-TBM as irradiation test bed and model verification
  • Other neutron irradiation devices and test facilities
  • Advanced microscopy and characterization methods
• Materials-design interface and interactions codes, standards, and standardization (SSTT).
  • Materials database development and material property handbooks
  • Advanced design methodologies and design criteria for future fusion facilities
  • Damage accumulation, interaction and critical failure modes
  • Development of test technologies towards standardization and norms including SSTT
  • Safety criteria and requirements
• Fundamental studies of radiation effects: modeling and experimental validation.
  • Multi-scale approaches and design of radiation resistant materials
  • Defect production and microstructural evolution
  • Fundamental helium, hydrogen, and tritium effects
  • Modeling and prediction of material property changes in fusion environment
• Cross-cutting issues and synergism with materials applications in other large-scale projects or highly loaded systems.
  • Cross-cutting material issues for fusion and fission nuclear power systems
  • Synergies with material development in other energy research communities
  • Education and training