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306 Fundamentals of Magnetic Thermonuclear Reactor Design
FIGURE 10.8 Toroidal cross-section of the outboard Li–V blanket sector of the Russian
DEMO-S reactor (the A–A section in Fig. 10.7).
10.4.2 Prospective Blanket Concepts
Prospective blanket concepts are based on extrapolation in structural material
properties and technology and on higher coolant exit temperatures, allowing a
greater conversion efficiency to be achieved (Table 10.3) [10]:
SSTR-2 (Japan): A helium-cooled ceramic blanket using silicon carbide
SiC /SiC as a structural material. The blanket consists of modules with alternat-
f
ing layers of beryllium, lithium ceramics (Li TiO or Li O) and silicon carbide
2
3
2
pebbles acting as a shield. Helium is used as a coolant for the FW and then for
the ceramic and beryllium layers.
