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6.1 What Makes a Good Fast Reactor Fuel?<br />

The ability to withstand the combination of high temperature and intense<br />

radiation is the characteristic of most importance in a fast reactor fuel. It means<br />

long life, and that, in turn, eases the load on the rest of the fuel cycle. The ability to<br />

generate high power without excessively high internal fuel temperatures is<br />

important too. Fast reactors generate their power with less tonnage of fuel than their<br />

thermal reactor counterpart. Paradoxically, the higher the enrichment, the less fuel<br />

you need. Instead of the three or four percent in the thermal reactor, enrichments in<br />

a fast reactor are in the range of twenty to twenty-five percent. The basic cross<br />

sections of all materials are small for fast neutrons, so the fraction of the fuel<br />

material that is fissile must make up for its smaller cross sections. With a lot of<br />

fissile material in each pin the power produced per pin must then be<br />

correspondingly high to minimize the total amount of fissile material required for a<br />

given power production. So the fuel must withstand high power densities as well as<br />

withstanding long irradiation times. The two are related, but they are not identical.<br />

The most basic feature is time in the reactor. The longer the fuel can remain in<br />

the reactor, the smaller the amount of fresh fuel needed. And for a system that<br />

recycles its fuel, like the IFR, this means the flows to spent fuel processing are<br />

smaller, which means smaller and cheaper processing and new fuel fabrication.<br />

Breeding new plutonium in the core means that the fissile content of the fuel stays<br />

fairly constant as the fuel burnup proceeds, so the flow of fissile material can be<br />

minimized only by long fuel residence times in the reactor.<br />

In theory, processing could be avoided completely by designing for very long<br />

fuel residence times indeed, up to the entire lifetime of the reactor, and periodically<br />

such systems are proposed. Generally the power densities allowed must be low. The<br />

phenomenon that normally limits fuel lifetime in a fast reactor is irradiation damage<br />

to the fuel cladding, and this directly limits the power density. Even with high<br />

breeding capability so adequate reactivity is maintained, the fuel lifetime is limited<br />

by the cladding. The intensity of the neutron flux and the length of the exposure to<br />

the flux—the ―fluence‖ as it is called—on the fuel cladding is what is important in<br />

limiting fuel life, not the fuel material itself. The result is that the power produced<br />

by such a reactor will be correspondingly low, or alternatively, a very much larger<br />

core, and thus a larger reactor vessel and components, will be needed. There isn‘t<br />

any way around this tradeoff. The construction cost of nuclear systems combined<br />

with low power production is deadly to plant economics.<br />

At the other extreme—and more realistic economically—was the scheme<br />

implemented by the designers of Experimental Breeder Reactor-II in the early<br />

1960s. As the metal fuel of those days couldn‘t withstand long residence times,<br />

their idea was to keep fuel in the reactor as high a percentage of the time as possible<br />

by rapidly processing it at low burnup and immediately returning it to the reactor.<br />

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