Author/Authors :
Poitevin، نويسنده , , Y. and Aubert، نويسنده , , Ph. and Diegele، نويسنده , , E. and de Dinechin، نويسنده , , G. and Rey، نويسنده , , J. and Rieth، نويسنده , , M. and Rigal، نويسنده , , E. and von der Weth، نويسنده , , A. and Boutard، نويسنده , , J.-L. and Tavassoli، نويسنده , , F.، نويسنده ,
Abstract :
Europe has developed two reference Tritium Breeder Blankets concepts for a DEMO fusion reactor: the Helium-Cooled Lithium–Lead and the Helium-Cooled Pebble-Bed. Both are using the reduced-activation ferritic–martensitic EUROFER-97 steel as structural material and will be tested in ITER under the form of test blanket modules. The fabrication of their EUROFER structures requires developing welding processes like laser, TIG, EB and diffusion welding often beyond the state-of-the-art. The status of European achievements in this area is reviewed, illustrating the variety of processes and key issues behind retained options, in particular with respect to metallurgical aspects and mechanical properties. Fabrication of mock-ups is highlighted and their characterization and performances with respect to design requirements are reviewed.
