21st International Conference on Fusion Reactor Materials

Start date
End date
Granada, Spain
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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