SFR (Gen IV)

The SFR systems are part of the GIF initiative. These are envisaged in two scales. The large one would incorporate a MOX fuel, supported by a reprocessing system serving a number of reactors. The second would be based on a Pu-minor actinide-zirconium metal alloy fuel, developed within a pyro-metallurgical process in co-located facilities (The US Generation IV Implementation Strategy, 2003). The outlet temperature would be

Table 12.5. Sodium-cooled fast reactors

Reactor

Rating (MWe)

Country

SFR (Gen IV med-large)

500-1500

GIF members

SFR (Gen IV small-med)

150-500

GIF members

EFR

1500

EU consortium

BN-800

800

Russia

DFBR

660

Japan

PFBR

500

India

image061

Figure 12.4. Sodium-cooled fast reactor. Source: NEA Annual Report (2002).

about 550°C. This system would mainly be used for electricity production or actinide burning. It is based on a closed fuel cycle, which is advantageous for actinide management. Both pool and loop type systems, the former shown in Figure 12.4, are possibly envisaged (Lennox, 2004).

The SFR concept takes advantage of the substantial expertise that has built up over many years of fast reactor operation in France, UK, US and elsewhere.

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