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EBR-II experience demonstrates that if the next sodium-cooled fast reactors are<br />

designed thoughtfully, and as designs evolve further, sodium-cooled fast reactors<br />

can have a very high level of reliability, maintainability, operability, and longevity.<br />

The basic design approach must be a simple, forgiving design, avoiding complexity<br />

and avoiding layers of safety systems, and made possible by its inherent safety<br />

features.<br />

Turning to the future prospects of fast reactors, some interest in fast reactors has<br />

been seen in recent years around the world, following the hiatus of the past two or<br />

three decades. In Russia, where BN-600 has been operating successfully over thirty<br />

years, and the construction of BN-800, originally planned in the 1980s, but caught<br />

up in the political maelstrom of the early ‗90s, was resumed a few years ago. It is<br />

now scheduled to be on-line around 2014. The China Institute of Atomic Energy<br />

(CIAE) has constructed the China Experimental Fast Reactor (CEFR), rated at 65<br />

MWth, 20 MWe (the capacity of EBR-II), which achieved criticality in 2010 and<br />

first power operation in 2011. China plans to construct two additional 800 MWe<br />

fast reactors by 2020 in cooperation with Russia. In India the Fast Breeder Test<br />

Reactor (FBTR) reached initial criticality in 1985 and has been operating<br />

successfully, including demonstration of a full carbide-fueled core. India is now<br />

building a 500 MWe Prototype Fast Breeder Reactor (PFBR), with commissioning<br />

targeted for 2014. Four more units of the same size are planned for completion by<br />

2020. Two sites have been designated for twin units each. India may well be the<br />

first nation in the world to establish a commercial fast reactor economy. Both<br />

France and Japan envision commercial fast reactors starting in 20452050 and to<br />

that end they plan prototype demonstration projects in the 20202025 time frame.<br />

South Korea is also developing a prototype sodium-cooled fast reactor toward the<br />

construction by 2028. [18-19]<br />

14.8 Typical Deployment Scenarios<br />

It is important to understand the effects of IFR deployments. To give an idea of<br />

its effect, we have considered deployment in the plausible nuclear growth scenario<br />

depicted in Figure 14-10. The World Nuclear Association surveyed member<br />

countries and compiled low and high estimates for nuclear capacity. [20] In 2030<br />

the low is 552 GWe, the high case 1,203 GWe. In 2060, the low and high cases are<br />

1,136 GWe and 3,488 GWe, and in 2100 they are 2,050 GWe and 11,000 GWe. In<br />

Figure 14-10, we took an average of the low case and the high case. This is not a<br />

forecast; our objective is to illustrate the limitations and impacts of a high IFR<br />

deployment rate on uranium resources.<br />

In Figure 14-10, nuclear expansion in the near term is assumed to be provided by<br />

the license extension (to sixty years) of the existing reactors plus the 1,575 GWe of<br />

new LWRs needed to meet the capacity assumed through 2050, taking into account<br />

326

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