Author/Authors :
Zmitko، نويسنده , , M. and Poitevin، نويسنده , , Y. and Boccaccini، نويسنده , , L. and Salavy، نويسنده , , J.-F. and Knitter، نويسنده , , R. and Mِslang، نويسنده , , A. and Magielsen، نويسنده , , A.J. and Hegeman، نويسنده , , J.B.J. and Lنsser، نويسنده , , R.، 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 will be tested in ITER under the form of Test Blanket Modules (TBMs). The paper reviews the current status of development and qualification of the EU TBMs functional materials; i.e. ceramic solid breeder materials, beryllium/beryllides multiplier materials and Lithium–Lead liquid metal breeder material Pb–15.7Li. For each functional material the main functional/performance requirements with key qualification issues, current status of the R&D activities and the EU development strategy are presented. In the development strategy major steps considered are listed pointing out importance of the ‘Development/qualification/procurement plan’, currently under elaboration, for definition of a roadmap of further activities aiming at delivery of qualified functional materials to be used in the European TBMs in ITER.
