21st International Conference on Fusion Reactor Materials
CIEMAT & IFMIF-DONES
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.
- 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