Objectives and status of EUROfusion DEMO blanket studies

• Published in: Fusion engineering and design Vol. 109-111; pp. 1199 - 1206
• Main Authors: Boccaccini, L.V., Aiello, G., Aubert, J., Bachmann, C., Barrett, T., Del Nevo, A., Demange, D., Forest, L., Hernandez, F., Norajitra, P., Porempovic, G., Rapisarda, D., Sardain, P., Utili, M., Vala, L.
• Format: Journal Article
• Language: English
• Published: Elsevier B.V 01.11.2016; Elsevier
• Subjects: Breeding blanket; DEMO; Engineering Sciences; In-vessel components; PbLi loops; Tokamak; Tritium extraction; Tokamak; PbLi loops; In-vessel components; Breeding blanket; DEMO; Tritium extraction; Breeding blanket; DEMO; Tokamak; In-vessel components; PbLi loops; Tritium extraction
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2015.12.054

•Short description of the new Breeding Blanket Project in the EUROfusion consortium for the design of the EU PPPT DEMO: objectives.•Presentation of the design approach used in the development of the Breeding Blanket design: requirements.•Breeding Blanket design; in particular the four blanket concepts included in the study are presented, recent results highlighted and the status discussed.•Auxiliary systems and related R&D programme: in particular the work areas addressed in the Project (Tritium Technology, Pb-Li and Solid Breeders Technology, First Wall Design and R&D, Manufacturing) are presented, recent results highlighted and the status discussed. The design of a DEMO reactor requires the design of a blanket system suitable of reliable T production and heat extraction for electricity production. In the frame of the EUROfusion Consortium activities, the Breeding Blanket Project has been constituted in 2014 with the goal to develop concepts of Breeding Blankets for the EU PPPT DEMO; this includes an integrated design and R&D programme with the goal to select after 2020 concepts on fusion plants for the engineering phase. The design activities are presently focalized around a pool of solid and liquid breeder blanket with helium, water and PbLi cooling. Development of tritium extraction and control technology, as well manufacturing and development of solid and PbLi breeders are part of the programme.