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ORNL-5388 - the Molten Salt Energy Technologies Web Site

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GRlBRLL 1<br />

U-239<br />

4-46<br />

As can be seen, <strong>the</strong> 239Pu content peaks at<br />

'~r 30 MWD/kg,decreasing <strong>the</strong>reafter. The<br />

higher Pu isotopes tend to peak at higher<br />

U-240 U-242 burnups so that at discharge 242Pu doniio.olG%,<br />

, nates. Compared to an LLJR with LEU ftlel,<br />

50 ,oo nwOlac <strong>the</strong> PBR v:ith HEU/Th fuel discharges only 8%<br />

HI)(II.TLUC"I.l.RuE1rEW.rT. as much fissile plutonium. Fur<strong>the</strong>rmore, <strong>the</strong><br />

Fig- 4-4-10 Buildup of <strong>the</strong> Plutoniur fissile fraction of <strong>the</strong> discharged plutonium<br />

Isotopic Composition in <strong>the</strong> MEU/Th Fuel.<br />

is only 39% compared to 71% for an LWR.<br />

Table 4.4-8 presents U308 requirements of <strong>the</strong> various once-through cycle^.^,^ The<br />

30-yr cumulative U308 demands for <strong>the</strong> MEU/Th once-through cycle and <strong>the</strong> HEU/Th once-<br />

through cycle were determined by explicit 30-yr calculations.8 The 30-yr cumulative U308<br />

demands for <strong>the</strong> LEU, <strong>the</strong> seed-and-breed MEU/Th and <strong>the</strong> seed-and-breed HEU/Th cycles were<br />

determined from <strong>the</strong> U308 demand for <strong>the</strong> equilibrium cycles and estimates of <strong>the</strong> inventory<br />

of <strong>the</strong> startup core and of <strong>the</strong> requirements for <strong>the</strong> approach to equilibrium.8<br />

As can be seen from Table 4.4-8, from <strong>the</strong> viewpoint of U308 utilization for oncethrough<br />

cycles in <strong>the</strong> PBR, LEU fuel is <strong>the</strong> least favorable and HEU/Th fuel is <strong>the</strong> most<br />

favorable with MEU/Th fuel having a U308 utilization between HEU/Th and LEU fuel. It should<br />

be noted that <strong>the</strong> cases presented in Table 4.4-8 do not include recycle of <strong>the</strong> bred fissile<br />

material. Under <strong>the</strong>se no-recycle constraints <strong>the</strong> MEU/Th cases have a 30-yr U3O8 demand comparable<br />

to a PWR operating with uranium and self-generated Pu recycle (see Case F, Table<br />

4.1-3). Thus if recycle were performed with <strong>the</strong> MEU/Th PBR cases, significantly less U308<br />

would be required than for <strong>the</strong> PWR with U and Pu recycle. One option for <strong>the</strong> recycle in <strong>the</strong><br />

seed-and-breed MEU/Th PBR case would be to cycle <strong>the</strong> fertile balls back into <strong>the</strong> feed stream<br />

(without reprocessing) for an additional pass through <strong>the</strong> pebble bed if <strong>the</strong> irradiation<br />

behavior of <strong>the</strong> fertile balls permits.<br />

Table 4.4-8. U308 Requirements for<br />

Once-Through PBR Cyclesa<br />

~-<br />

Case 1, Case 2, Case 3, Case 4, Case 5,<br />

Seed and Ereed Seed and Greed<br />

LEU 11 E U / T h MEU/Th HEU/Th HEU/Th<br />

Eauilihriun cycle 143 135 137 126 126<br />

U308 demand, ST/GWE-yr<br />

30-year cumulative<br />

U308 demand,b ST/GWE 45OOc 41 84d 4200' 4007d 40OOc<br />

'The basis for <strong>the</strong>se requirements is a lOCO-H'.le plant operating at 752 capacity<br />

factor for 30 years; tails composition is assumed to be 0.2 w/o.<br />

'Assures no recycle.<br />

c<br />

Estimated value; could differ from an explicit 30-yr calculation by 5 3%.<br />

dExplicit 30-yr calculation.<br />

L<br />

L

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