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LNF:Technology: Difference between revisions
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The main goal of the Fusion Technology Division of the Spanish National Fusion Laboratory is research on the properties as well as the radiation hardness and subsequent degradation of structural and functional materials for future fusion reactors. In particular, studies on reduced activity ferritic/martensitic steels and materials used for electrical isolation, diagnostic windows etc. are central to this work. In parallel, given that at present, there is no neutron source available that simulates the fluxes and energies required for material irradiation under predicted fusion reactor conditions, the division is involved in the development of suitable neutron sources for material irradiation (ENS, IFMIF, and DONES). These sources, when on-line, will facilitate accelerated irradiation damage studies in materials of interest. Finally, activities by the division in the area of lithium breeding blanket (LLB) development can be highlighted. This work is based on liquid metals (Li-Pb) or lithium based ceramics for LLB and on corrosion or permeation phenomena in blanket structural materials. | The main goal of the Fusion Technology Division of the Spanish National Fusion Laboratory is research on the properties as well as the radiation hardness and subsequent degradation of structural and functional materials for future fusion reactors. In particular, studies on reduced activity ferritic/martensitic steels and materials used for electrical isolation, diagnostic windows etc. are central to this work. In parallel, given that at present, there is no neutron source available that simulates the fluxes and energies required for material irradiation under predicted fusion reactor conditions, the division is involved in the development of suitable neutron sources for material irradiation (ENS, IFMIF, and DONES). These sources, when on-line, will facilitate accelerated irradiation damage studies in materials of interest. Finally, activities by the division in the area of lithium breeding blanket (LLB) development can be highlighted. This work is based on liquid metals (Li-Pb) or lithium based ceramics for LLB and on corrosion or permeation phenomena in blanket structural materials. | ||
==Materials for fusion applications== | ==Materials for fusion applications== | ||
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*Structural Materials: Candidate steels to build the reactor vessel while resisting loads, high temperatures, high radiation fluxes and intense magnetic fields. | *Structural Materials: Candidate steels to build the reactor vessel while resisting loads, high temperatures, high radiation fluxes and intense magnetic fields. | ||
*Materials for solid breeder blankets: For the HCPB (Helium Cooled Pebble Bed) design. | *Materials for solid breeder blankets: For the HCPB (Helium Cooled Pebble Bed) design. | ||
==Material Irradiation Facilities== | ==Material Irradiation Facilities== | ||
===2 MeV ELECTRON VAN DER GRAAF ACCELERATOR=== | ===2 MeV ELECTRON VAN DER GRAAF ACCELERATOR=== | ||
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In-situ measurement capability and expertise. | In-situ measurement capability and expertise. | ||
At this facility different studies on candidate fusion insulators have been carried out, in particular electrical, optical and hydrogen and helium diffusion properties are measured regularly in-situ. These studies are carried out at controlled temperature, from liquid nitrogen up to 1000 C. Available special irradiation chambers and sample holders have been designed by the implanter staff and fabricated at the Ciemat workshops. | At this facility different studies on candidate fusion insulators have been carried out, in particular electrical, optical and hydrogen and helium diffusion properties are measured regularly in-situ. These studies are carried out at controlled temperature, from liquid nitrogen up to 1000 C. Available special irradiation chambers and sample holders have been designed by the implanter staff and fabricated at the Ciemat workshops. | ||
===NAYADE Co-60 irradiation facility=== | ===NAYADE Co-60 irradiation facility=== | ||