A conceptual study of DEMO-S steady state reactor is being carried out in R
F. The main goals of the study are aimed at establishing physics and engine
ering basis and limitations of the reactor. It was assumed that DEMO is a n
ext step after international thermonuclear experimental reactors (ITER) ope
ration, and so conservative assumptions were used in the study based on ITE
R engineering. A steady state operation mode is recommended with fusion pow
er of 2-3 GW and maximum first wall (FW) neutron load of 3-4 MW m(-2). The
reactor has to operate in advance plasma mode with high fraction of bootstr
ap current. The reversed shear regime and operation in H-mode are evaluated
. A lifetime of 30-40 MW m(-2) is assumed for the DEMO plant, with three to
four changes of plasma facing components. The general reactor layout is de
termined. Two options of breeding blanket with ceramic and liquid lithium b
reeders are presented, supported by neutronic, thermalhydraulic and mechani
cal calculations. A conventional type of water or Li cooling divertor targe
ts with maximum heat load of similar to 10 MW m(-2) was chosen. Heat to ele
ctricity conversion schemes are analysed for both helium and liquid metal c
oolant with net efficiency of 35-40%. Aspects of radioactive waste manageme
nt are considered. (C) 2000 Elsevier Science B.V. Ail rights reserved.