Community Research and Development Information Service - CORDIS


The European R&D programme in support of the development of water-cooled Pb-17Li blankets for DEMO aims at improving the database concerning tritium behaviour and compatibility between blanket materials. The four main areas of the experimental programme are structural material corrosion by Pb-17Li, tritium extraction and permeation control, Pb-17Li physico-chemistry, and water/Pb-17Li interaction. This paper describes the most significant results obtained to date in the various experiments performed in Europe and the future programme required to complete the database by 1994.

Additional information

Authors: GIANCARLI L ET AL., CEA, CEN Saclay, Gif-sur-Yvette (FR);BARBIER F ET AL., CEA, CEN Fontenay-aux-Roses (FR);COEN V ET AL., JRC Ispra (IT);BENAMATI G, ENEA, Dipartimento Fusione Brasimone, Camugnano (IT);AGOSTINI P, ENEA, Dipartimento Fusione Brasimone, Camugnano (IT)
Bibliographic Reference: Paper presented: 10th Topical Meeting on the Technology of Fusion Energy, Boston (US), June 7-12, 1992
Availability: Available from (1) as Paper EN 37492 ORA
Record Number: 199310716 / Last updated on: 1994-11-29
Original language: en
Available languages: en
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