ORNL-5388 - the Molten Salt Energy Technologies Web Site
ORNL-5388 - the Molten Salt Energy Technologies Web Site
ORNL-5388 - the Molten Salt Energy Technologies Web Site
Create successful ePaper yourself
Turn your PDF publications into a flip-book with our unique Google optimized e-Paper software.
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 />
L