17th International Conference on Fusion Reactor Materials

会议主题： 1、Advanced materials development, including fabricationand joining Ferritic/martensitic steels Advanced steels, ODS steels Ceramics, ceramic composites and other low-Z materials Tungsten, refractory alloys and other high-Z materials Vanadium and its alloys Other structural alloys 2、Fusion-specific applications of materials Plasma-facing materials High heat flux materials Radiation resistant materials Breeding and multiplying materials Insulating materials Plasma-diagnostic system materials Magnet materials 3、Materials technologies and testing in IFMIF, ITER and beyond Test blanket module material technologies and issues ITER material technologies and issues IFMIF and other intense fusion neutron sources 4、Materials design interface issues Codes, standards, and materials databases Safety criteria and requirements 5、Fundamentals of radiation effects and advanced characterization Defect production and properties Microstructural evolution Mechanical property changes Fundamental helium, hydrogen, and tritium effects Advanced characterization and specimen test technology 6、Multi-scale modelling Multi-scale modelling for design Modelling to predict the performance of fusion materials and systems New developments of multi-scale approaches for designing radiation resistant materials 7、Environmental effects Tritium retention and transport Oxidation and corrosion Chemical compatibility Barrier coatings 8、Programs and strategies Cross-cutting approaches Cross-cutting materials issues for fusion and fission nuclear power-systems The Broader Approach and other international collaborations Education and training