A water-cooled and austenitic stainless-steel-structured breeding blan
ket system is designed for a volumetric neutron source (VNS), based on
a steady-state tokamak device. The designed VNS with super-conducting
coils has a 4.5 m main radius and a total of 300 MW in fusion power.
It yields the tritium consumption of approximately 10 kg per year with
50% availability. It is unrealistic to assume that this amount of tri
tium could be supplied by other nuclear facilities, therefore, tritium
breeding with the VNS device itself should be accommodated. The capab
ility of tritium breeding for the Li-Pb breeder is examined. Compared
to ceramic breeding materials, in general, the Li,,Pb,, breeder has th
e potential for a higher tritium breeding ratio. In addition, the comp
atibility of Li-Pb with water coolant and with structure material at l
ow temperature and low flow velocity may be acceptable. The calculated
local TBR in the present design reached 1.4 or more in the Li-Pb bree
der with a sufficient thickness of the breeding zone. The temperature
distribution in the breeding region of the Li-Pb blanket was controlle
d to avoid corrosion of the structure material, using a double-walled
cooling panel. The net TBR might attain the acceptable value when only
the outboard Li-Pb blanket is used, since the contribution of outboar
d blanket to tritium breeding is higher than its coverage. (C) 1998 El
sevier Science S.A. All rights reserved.