AbstractThe future fusion reactor fuel will be a mixture of deuterium and tritium. Deuterium is produced using traditional separation technology. Tritium, on the contrary, 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 membranes reaction/separation units, is studied in this work. The first considered membrane unit is a catalytic ceramic membrane reactor to remove, via oxidation, the hydrogen isotopes from the purge gas (He); the second is a Pd/Ag membrane permeator to separate the hydrogen isotopes from the water shift reactor gaseus products.The modelling and the mass balances have been obtained either on the basis of data in the literature or on experimental results.