Two blanket options are considered for RF DEMO-S reactor (fusion power simi
lar to2.4 GW) with steady-state operation: lithium (Li) self-cooled and cer
amic breeder helium-cooled ones. Lithium-cooled blanket, which uses Li as c
oolant and tritium breeder and V-Cr-Ti (vanadium-chrome-titanium) alloy as
structural material, is described here. Poloidal type of Li flow is chosen
under the assumption that electroinsulating coating is developed on the int
erface of Li/structure material. Results of preliminary neutronic, thermal-
hydraulic and stress analysis are presented. The steam turbine cycle conver
ting the thermal to electric energy is recommended with intermediate sodium
loop on the basis of the FBR experience. (C) 2000 Elsevier Science B.V. Al
l rights reserved.