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ORNL-5388 - the Molten Salt Energy Technologies Web Site

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7-1 2<br />

If <strong>the</strong>se once-through systems are operating on <strong>the</strong> throwaway option, <strong>the</strong> fissile<br />

material discharged in <strong>the</strong>ir spent fuel elements is deemed unusable; in fact, no value is<br />

assigned to <strong>the</strong> spent fuel in once-through fuel cycle accounting. Thus, in this case <strong>the</strong><br />

most resource-efficient once-through fuel cycle is <strong>the</strong> one that requires <strong>the</strong> lowest fissile<br />

charge per unit power. If, however, a capability for reprocessing <strong>the</strong> spent fuel is<br />

eventually envisioned (i.e., if <strong>the</strong> throwaway option becomes a stowaway option), <strong>the</strong>n <strong>the</strong><br />

quantity of fissile material in <strong>the</strong> spent fuel becomes an important consideration. Esti-<br />

mates of <strong>the</strong> amounts of <strong>the</strong> various fissile materials discharged by each reactor type<br />

operating on both <strong>the</strong> LEU cycle and <strong>the</strong> MEU(235)/Th cycle are given in Table 7.2-2.<br />

~<br />

Table 7.2.2. 30-Year Charge and Discharge Quanti ties<br />

for Once-Through Fuel Cyclesa<br />

235u<br />

MTIGWe<br />

Fi ssi 1 e Discharge<br />

b<br />

Total<br />

Cumulative<br />

Net Fissile<br />

Reactor Charge 233U 23% Puf Fissile Consumption<br />

PWR<br />

HllR<br />

HTGR<br />

PBR<br />

SSCR<br />

PWR<br />

HWR<br />

HTGR<br />

PBR<br />

24.72<br />

17.53<br />

19.49<br />

18.09<br />

22.25<br />

33.83<br />

32.63<br />

17.99<br />

16.55<br />

LEU Cycle<br />

- 6.45 5.22<br />

- 1.77 5.49<br />

- 3.25 2.16<br />

- 2.79 1.89<br />

. 5.46 5.88<br />

MEU(235)/Th Cycle<br />

7.80 11.52 2.13<br />

14.28 10.08 0.75<br />

2.31 1.35 0.69<br />

2.73 1.17 0.42<br />

a<br />

bAt 75% caDacitv factor.<br />

Estimated from -equilibrium cycle.<br />

11.67 13.05<br />

7.26 10.37<br />

5.41 14.08<br />

4.68 13.41<br />

11.34 10.91<br />

21.45 12.38<br />

25.11 7.52<br />

4.35 13.64<br />

4.32 12.23<br />

For <strong>the</strong> PUR and HWR, <strong>the</strong> use of <strong>the</strong> MEU/Th fuel cycle ra<strong>the</strong>r than <strong>the</strong> LEU fuel<br />

cycle results in a significant increase in <strong>the</strong> amount of fissile material contained in<br />

<strong>the</strong> spent fuel. It should be noted, however, that this increase is primarily <strong>the</strong> result<br />

of higher feed requirements (i-e., 235U commitment). In contrast, converting from <strong>the</strong><br />

LEU cycle to <strong>the</strong> MEU/Th cycle does not materially affect <strong>the</strong> net consumption of <strong>the</strong> gas-<br />

cooled HTGR and PBR (although it dramatically affects <strong>the</strong> types of fissile material pre-<br />

sent in <strong>the</strong>ir spent fuel). The relatively low values for <strong>the</strong> discharge quantities for <strong>the</strong><br />

gas-cooled reactors is <strong>the</strong> result of two effects: a lower initial loading; and a design<br />

that is apparently based on higher burnup, which in turn reduces <strong>the</strong> amount of fissile<br />

material discharged. Finally, it is to be remembered that <strong>the</strong> resources represented by <strong>the</strong><br />

spent fuel inventory are recoverable only when <strong>the</strong> spent fuel is reprocessed, whereas <strong>the</strong><br />

U308 commitment is necessary throughout <strong>the</strong> operating lifetime of <strong>the</strong> reactor. Thus, in a<br />

sense, <strong>the</strong> spent fuel resource must be discounted in time to order to assess <strong>the</strong> best system<br />

from a resource utilization basis.<br />

I;'<br />

I;<br />

i;<br />

L<br />

c<br />

c<br />

L<br />

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