Abstract
Two methods to recover the tritium from the Li 17 Pb 83 liquid breeder used in the breeding blanket design developed at JRC-Ispra for INTOR/NET [1] are outlined and discussed. They are (i) direct tritium pumping from stagnant and stirred breeder, and (ii) tritium extraction from a packed or bubble column by flushing an inert gas in counter-current to the breeder. The lack of experimental data on tritium solubility and diffusion and on other physico-chemical properties of Li 17 Pb 83 do not yet enable us to choose among the two schemes. However, at present the second appears more promising.
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