Community Research and Development Information Service - CORDIS


The fuel of future fusion reactors will be a mixture of deuterium and tritium. The deuterium is available by means of the traditional separation technology. The tritium, however, must be produced by means of a nuclear reaction between neutrons and lithium atoms within the reactor breeder which could be a lithiated ceramic material or a liquid metal containing lithium. The tritium produced in the breeder needs a proper extraction process to reach the required purity level. A conceptual modified version of the tritium recovery plant for a solid ceramic breeder, working with two membrane reaction/separation units, is studied in this work. The first membrane unit considered is a catalytic ceramic membrane reactor to remove, via oxidation, the hydrogen isotopes from the purge gas (He), while the second is a Pd/Ag membrane permeator to separate the hydrogen isotopes from the water shift reactor gaseous products.

Additional information

Authors: VIOLANTE V, ENEA, Centro Ricerche Energia Frascati, Roma (IT);BASILE A, CNR, Istituto di Ricerci su Membrane e Reattori Chimici, Cosenza (IT);DRIOLI E, Università della Calabria (IT)
Bibliographic Reference: Report: RT/NUCL/92/02 EN (1992) 18 pp.
Availability: Available from Servizio Studi e Documentazione, ENEA, Centro Ricerche Energia Frascati, C.P. 65-00044 Frascati, Roma (IT)
Record Number: 199310613 / Last updated on: 1994-11-29
Original language: en
Available languages: en