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neutron leakages from the core are a lot less than from the top and bottom (the<br />

diameter of the core as a rule is at least double the height), the optimum radial<br />

blanket thickness even for maximum breeding is only two or three layers. And for<br />

self-sustaining reactivity only, perhaps one layer of external blanket is necessary; a<br />

net burner of actinides will have no uranium blankets at all, only steel shielding.<br />

The core layout presented in Figure 14-4 is for a 350 MWe reactor core. Size is<br />

determined by the number of fuel assemblies; the assembly design itself probably<br />

remains the same.<br />

14.4.4 Reactor Size Effects<br />

The unit lattice cell design principles described in the previous section are<br />

applicable independent of the reactor power. Larger reactors require more unit cells<br />

or more fuel pins and assemblies. The core size can grow in both radial and axial<br />

directions. But when the core size grows to about three feet in height, any further<br />

expansion is in the radial direction. Even with a three-foot active fuel column<br />

length, the overall assembly length could be more than twelve or thirteen feet when<br />

the gas plenum, upper and lower shields (or blankets), and inlet and outlet nozzles<br />

are added. Since the spent fuel has to be handled under sodium when transferred<br />

across the core, the sodium pool depth and the vessel height have to be increased as<br />

the active core height increases. But the three-foot optimum is not set in concrete.<br />

Both the height and the diameter can differ with the same design for electrical<br />

output if different properties of the core are emphasized. But a typical core diameter<br />

would be about ten feet for a 350 MWe plant and some fifteen feet or so for a 1,000<br />

MWe, both with core heights of about three feet.<br />

A key question in the effects of reactor size is whether the inherent safety<br />

features demonstrated in the small EBR-II can be achieved in larger reactor sizes, or<br />

if indeed there is a size limit for such behavior. Some inherent safety characteristics<br />

sought in other reactor concepts, such as the radiative heat removal, do depend on<br />

the reactor size. However, the IFR‘s inherent safety is more or less independent of<br />

the reactor size. As explained in detail in Section 7.8, this independence is due to<br />

the reactivity feedback mechanisms themselves being quite independent of the<br />

reactor size. The net result is that the margins to coolant boiling during unprotected<br />

loss-of-flow and unprotected loss-of-heat-sink events are very similar independent<br />

of reactor size, as presented in Table 7-1.<br />

One important effect of reactor size is its effect on the specific fissile inventory<br />

requirement. Since the unit cell design remains the same, the total amount of heavy<br />

metal increases directly proportional to the reactor power. However, the fissile mass<br />

does not follow this proportionality, since the fissile enrichment (ratio of fissile<br />

mass to heavy metal mass) is reduced due to the reduced neutron leakage of a larger<br />

core. More neutrons are then available inside the core for in situ breeding, which<br />

further reduces the enrichment level. The amount of fuel needed for a given power<br />

315

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