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The FuTure oF nuclear Fuel cycle - MIT Energy Initiative

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advanced technology opportunities<br />

<strong>The</strong> united States has not made significant investments in<br />

understanding fuel <strong>cycle</strong> options for several decades. In this<br />

time new options (appendix B) with potentially better characteristics<br />

but major uncertainties have been partly developed.<br />

Several of these are described here.<br />

LWRs with modified cores. <strong>The</strong> appeal of liquid-metal<br />

cooled fast reactors (lMFrs) is that they enable a closed fuel<br />

<strong>cycle</strong> that extracts 50 times as much energy from uranium<br />

as does the once-through (open) fuel <strong>cycle</strong> of existing lWrs.<br />

But demonstration lMFrs to-date have been more expensive<br />

compared to existing light water reactors (lWrs) and<br />

so have never been commercialized. <strong>The</strong> sodium fast reactor<br />

was chosen in the 1970s as the preferred sustainable reactor<br />

because of its high conversion ratio. our analysis indicates<br />

that a lower conversion ratio near unity is preferable for a<br />

sustainable reactor. advances in the design now indicate<br />

that a hard-spectrum lWr could have a conversion ratio<br />

near unity and be a sustainable reactor. Such modified-core<br />

lWrs are likely to be less costly to develop than lMFrs, because<br />

only the reactor core needs to change, and may be<br />

more economic to operate. Moreover, this approach may<br />

provide the option of using some of the existing reactor<br />

fleet for a closed, sustainable fuel <strong>cycle</strong> that would greatly<br />

extend uranium resources. <strong>The</strong>re has been significant work<br />

in several countries on such modified-core lWrs, but additional<br />

research and demonstration would be required to<br />

determine commercial viability.<br />

Advanced High-Temperature Reactors. In the last decade,<br />

a new reactor concept has been proposed that uses liquid<br />

fluoride salts as coolants and graphite-matrix coated-particle<br />

fuel. <strong>The</strong> reactor combines the coolant developed for<br />

molten-salt reactors and the fuel developed for gas-cooled<br />

high-temperature reactors. one variant uses pebble-bed<br />

graphite-matrix coated-particle fuel. With this option, the<br />

fuel pebbles would not be fixed in place as with a conventional<br />

fuel assembly, but would slowly move through the<br />

reactor core. This allows continuous re-fueling and three<br />

dimensional optimization of the reactor over time, enabling<br />

novel fuel <strong>cycle</strong>s. For example, such a reactor may<br />

be operated in a combined uranium-thorium fuel <strong>cycle</strong> in<br />

a once-through mode or may have a high conversion ratio<br />

(near unity) if operated with a closed fuel <strong>cycle</strong>. <strong>The</strong> reactor<br />

would operate at low pressures and with high coolant temperatures<br />

resulting in increased efficiency of electric power<br />

generation. Thus such reactors could have lower capital<br />

costs and enhanced safety and nonproliferation characteristics<br />

relative to lWrs. rd&d would be needed to determine<br />

long-term commercial viability. This reactor is also called the<br />

fluoride salt high-temperature reactor.<br />

Uranium from Seawater. Seawater contains about four<br />

billion tons of uranium, enough to support thousands of<br />

reactors for thousands of years. recent Japanese research<br />

suggests that the cost of obtaining uranium from seawater<br />

may ultimately be low enough to be commercially feasible,<br />

which would enable once-through fuel <strong>cycle</strong>s for centuries.<br />

<strong>The</strong> economic viability of this option depends upon the<br />

long-term durability in seawater of the ion exchanger that is<br />

used to separate uranium. r&d is required to determine the<br />

potential for seawater uranium.<br />

Nuclear renewable futures. historically, <strong>nuclear</strong> energy<br />

has been considered as a source of base-load electricity,<br />

which constitutes a quarter to a third of the world’s total<br />

energy needs. however, there are additional candidate markets,<br />

such as meeting peak and other variable electricity<br />

demands by coupling base-load <strong>nuclear</strong> reactors to huge<br />

energy storage systems, or production of renewable liquid<br />

fuels in <strong>nuclear</strong>-powered biorefineries. Viability depends<br />

upon both the economics of <strong>nuclear</strong> power and successful<br />

development and commercialization of technologies such<br />

as gigawatt-year heat storage, high-temperature electrolysis<br />

for hydrogen production, and hydrocracking of lignin.<br />

developments in this area could significantly expand lowcarbon<br />

energy options for the united States and may drive<br />

market requirements (temperature of delivered heat, reactor<br />

size, etc.) that, in turn, would drive reactor and fuel <strong>cycle</strong><br />

decisions.<br />

chapter 10. recommended analysis, research, development, and demonstration Programs 141

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