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Zmitko M.,Fusion for Energy F4E | Poitevin Y.,Fusion for Energy F4E | Boccaccini L.,Institute fuer Neutronenphysik und Reaktortechnik | Salavy J.-F.,CEA Saclay Nuclear Research Center | And 5 more authors.
Journal of Nuclear Materials | Year: 2011

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. © 2011 Elsevier B.V. All rights reserved. Source


Poitevin Y.,Fusion for Energy F4E | Aubert P.,CEA Saclay Nuclear Research Center | Diegele E.,Fusion for Energy F4E | De Dinechin G.,CEA Saclay Nuclear Research Center | And 6 more authors.
Journal of Nuclear Materials | Year: 2011

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. © 2010 Elsevier B.V. All rights reserved. Source


Poitevin Y.,Fusion for Energy F4E | Boccaccini L.V.,Institute fuer Neutronenphysik und Reaktortechnik | Zmitko M.,Fusion for Energy F4E | Ricapito I.,Fusion for Energy F4E | And 7 more authors.
Fusion Engineering and Design | Year: 2010

Europe has developed two reference tritium breeder blankets concepts that will be tested in ITER under the form of Test Blanket Modules: (i) the Helium-Cooled Lithium-Lead which uses the liquid Pb-15.7Li as both breeder and neutron multiplier, (ii) the Helium-Cooled Pebble-Bed with lithiated ceramic pebbles as breeder and beryllium pebbles as neutron multiplier. An extensive development program has been carried-out over the last decade combining experimental and numerical simulations aimed at identifying and quantifying physical phenomena occurring in breeder blankets and at optimizing their design and technologies accordingly. On this basis, sound guidelines for the design and technological choices of Test Blanket Modules can be derived. In addition, regulatory and ITER project requirements, which prefigure the future DEMO blanket ones, are now integrated in the development and qualification program of the Test Blanket Modules. Their scope and implication are analyzed. © 2010 Published by Elsevier B.V. All rights reserved. Source

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