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PLENTIFUL ENERGY

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core is around 150 o C. For higher temperature rises, the coolant mass flow rate can<br />

be reduced, but this results in a higher thermal stress on cladding and a greater<br />

difference in outlet temperatures between adjacent assemblies. This can lead to<br />

thermal striping (a random joining of hot and cold flows, leading to cyclical stresses<br />

that contribute to fatigue cracking) on upper internal structures.<br />

14.4.3 Design Tradeoffs<br />

As discussed above, the selection of linear heat rate and temperature rise involve<br />

tradeoffs. Tradeoffs continue as the design progresses. For a given linear heat rate<br />

and temperature rise, the mass flow rate is determined by the heat balance equation.<br />

The coolant area of the unit lattice cell is then given by the mass flow rate divided<br />

by the coolant velocity. Higher coolant velocities reduce the coolant area and<br />

increase the fuel volume fraction. However, the pressure drop increases<br />

(proportional to the square of the velocity), which in turn increases pumping power<br />

requirements and reduces natural circulation tendency. Therefore, the coolant<br />

velocity is restricted by the need to keep the pressure drop below a given target<br />

value. For the design parameters presented in Table 14-3, a linear rate of 30.8<br />

kW/m, a temperature rise of 155 o C, and a pressure drop of 15 psi were taken. For a<br />

given pin diameter, the coolant area can be calculated and the unit lattice<br />

configuration is fixed to arrive at the volume fractions of fuel, coolant and<br />

structures.<br />

A cladding thickness of 0.05 cm, hexagonal duct wall thickness of 0.3 cm, and<br />

wirewrap spacers as illustrated in Figure 14-3 are reasonable choices, as is the<br />

choice of 169 pins per fuel assembly. The number of pins for n-hexagonal arrays is<br />

given by 3n(n-1)+1, and illustrated in Table 14-4. If the number of pins per<br />

assembly is increased to 217, the structural fraction is further reduced and the fuel<br />

volume fraction is increased, as shown in Figure 14-5. The assembly weight is also<br />

increased, and this places additional burden on the in-vessel fuel handling machine.<br />

Also the number of the assemblies for the entire core is reduced, which results in<br />

less flexibility in optimizing the number and location of the control rods. In general,<br />

a smaller reactor has a smaller number of pins per assembly, and as the reactor size<br />

increases the number of pins per assembly increases.<br />

In general, the higher fuel volume fraction design gives better neutron economy,<br />

resulting in lower fissile enrichment, a higher internal conversion ratio, and a<br />

reduced reactivity swing during burnup. By minimizing the initial excess reactivity<br />

requirements, the control rod requirement is reduced and accidental reactivity<br />

insertion events are more easily handled. In general, the excess reactivity<br />

requirements for the IFR are much less than those of thermal reactors, as illustrated<br />

in Figure 14-6. In a thermal spectrum, the reactivity change between refueling<br />

intervals is rather large, and in addition, the buildup of fission products such as Xe<br />

and Sm consume significant amount of reactivity. The thermal reactor core must<br />

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