Blankets and diverters are the key components of a fusion power plant due t
o their large impact on the overall plant design, performance and availabil
ity, and on the cost of electricity. This paper recalls the main features o
f the TAURO blanket, a self-cooled Pb-17Li concept using SiCf/SiC composite
as structural material, and describes the most recent thermo-mechanical an
alyses performed on the blanket. It includes an evaluation of a liquid-meta
l cooled divertor which could be associated with such a blanket. Investigat
ions were carried out to determine the potential and limits of the blanket
and of a liquid-metal cooled divertor in terms of maximum acceptable surfac
e heat flux. The high outlet temperature of the Pb-17Li coolant (800 degree
sC) leads to an attractive energy conversion efficiency (>47%) assuming hel
ium-coolant for the secondary circuit. Special heat exchangers, using SiCf/
SiC tubes are envisaged. Thermo-mechanical analyses have pointed out that m
aximum surface heat flux on FW and divertor could be about 0.65 and < 5 MW/
m(2), respectively. It is expected that an improvement of the SiCf/SiC mode
ling, taking into account non linear behavior presently under way, and the
use of design criteria adapted to more advanced composites could allow even
higher limits. (C) 2000 Elsevier Science B.V. All rights reserved.