Development of welding technologies for the manufacturing of European Tritium Breeder blanket modules

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 for...

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Veröffentlicht in:	Journal of nuclear materials 2011-10, Vol.417 (1-3), p.36-42
Hauptverfasser:	Poitevin, Y., Aubert, Ph, Diegele, E., de Dinechin, G., Rey, J., Rieth, M., Rigal, E., von der Weth, A., Boutard, J.-L., Tavassoli, F.
Format:	Artikel
Sprache:	eng
Schlagworte:	Applied sciences Blanketing Controled nuclear fusion plants Diffusion welding Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Fuels Installations for energy generation and conversion: thermal and electrical energy Mechanical properties Modules Nuclear fuels State of the art Structural steels Tritium Welding
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