The question of the tritium recovery in water-cooled Pb17Li blankets h
as been under investigation for several years at JRC Ispra. The method
which has been more extensively analysed is that of slowly circulatin
g the breeder out from the blanket units and of extracting the tritium
from it outside the plasma vacuum vessel by helium gas purging or vac
uum degassing in a suited process apparatus. A computerized model of t
he tritium behaviour in the blanket units and in the extraction system
was developed. It includes four submodels: (1) tritium permeation pro
cess from the breeder to the cooling water as a function of the local
operative conditions (tritium concentration in Pb17Li, breeder tempera
ture and flow rate); (2) tritium mass balance in each breeding unit; (
3) tritium desorption from the breeder material to the gas phase of th
e extraction system; (4) tritium extraction efficiency as a function o
f the design parameters of the recovery apparatus. In the present pape
r, on the basis of this model, a parametric study of the tritium perme
ation rate in the cooling water and of the tritium inventory in the bl
anket is carried out. Results are reported and discussed in terms of d
imensionless groups which describe the relative effects of the overall
resistance on tritium transfer to the cooling water (with and without
permeation barriers), circulating Pb17Li flow rate and extraction eff
iciency of the tritium recovery unit. The parametric study is extended
to the recovery unit in the case of tritium extraction by helium purg
e or vacuum degassing in a droplet spray unit.