DEVELOPMENT OF CERAMIC TRITIUM BREEDING MATERIALS, IRRADIATION TESTING AND TRITIUM RECOVERY
In D-T fusion reactors, tritium is required to supply the fuel for the plasma. One of the most promising concepts for providing a source of tritium is to surround the plasma with a blanket material composed of a lithium ceramic. A carrier gas would sweep tritium produced by fusion neutrons to processing equipment. A major concern is that tritium release may not be high enough to provide a continuous supply of tritium through the carrier gas. Also, few irradiation data are available on the lithium ceramics considered, i.e. Li-20, LiA10-2, Li-2Si0-3. Layout studies, calculations and design considerations have been started for the irradiation of these blanket materials in the HFR Petten, to investigate the physical chemical material properties and tritium release behaviour at a variety of irradiation parameters, e.g. temperature, burn-up, heating rate, etc. This paper was presented during the Ceramics Breeding Materials Workshop, organised by the Commission of the European Communities in order to establish the frame for a blanket material programme within the 1982 - 1986 European Fusion Technology Programme.
Bibliographic Reference: CERAMICS BREEDING MATERIALS WORKSHOP, GARCHING (GERMANY), MAY 17-18, 1983 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 31538 ORA
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Record Number: 1989122072800 / Last updated on: 1987-01-01
Available languages: en