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ORNL-5388 - the Molten Salt Energy Technologies Web Site

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lm, 1 I I I I<br />

mf RR WITH UGHT rwrmiw TMMMUTATICU<br />

Fig. 6.2-29. The Nuclear Contribution<br />

of an LWR-FBR System with Light Plutonium<br />

"Transmutation1' (High-Cost U308 Supply).<br />

wf u - nif RR mm LIGHT MCUIUH TMMMUI*TION<br />

I I , I I L I<br />

0 I9e4 I990 mx, 1010 ma 2010 )Du) Iow<br />

Fig. 6.2-31. Relative Nuclear Contri-<br />

butions of Each Reactor Type in LWR-FBR<br />

System with Light Plutonium "Transmutation"<br />

(High-Cost U308 Supply).<br />

Y€AR<br />

6-42<br />

I I I I I I<br />

YEAR<br />

Fig. 6.2-30. Relative Nuclear Contri-<br />

butions of Reactors Located Inside (Pu-Fueled)<br />

and Outside (Denatured LWRs) <strong>Energy</strong> Centers<br />

(High-Cost U308 Supply).<br />

for <strong>the</strong> LWR loaded with approximately 3% en-<br />

riched 235U in ei<strong>the</strong>r case is approximately<br />

420 GWe. However, in this option, as <strong>the</strong> in-<br />

stalled capacity of <strong>the</strong> 235U-loaded LWRs<br />

decreases, <strong>the</strong> energy center FBRs produce in-<br />

creasing amounts of 233U for <strong>the</strong> denatured LWRs,<br />

and thus <strong>the</strong> total installed nuclear capacity con-<br />

tinues to increase at a net rate of 15 GWe/yr.<br />

The amount of fissile plutonium that must<br />

be handled in <strong>the</strong> energy centers as fresh fuel<br />

each year is shown in Fig. 6.2-32.<br />

Approxi-<br />

mately 620 kg of fissile plutonium per GWe must<br />

be handled in this case, as compared to approxi-<br />

mately 170 kg of fissile plutonium in fresh fuel per GWe each year for <strong>the</strong> case of plutonium<br />

minimization and utilization. Thus, it appears that <strong>the</strong> ability to maintain an energy support<br />

ratio greater than unity while simultaneously adding 15 GWe/yr will necessitate handling more<br />

fissile plutonium in fresh fuel in <strong>the</strong> energy centers.<br />

As pointed out'in previous cases, <strong>the</strong> ability to maintain a high energy support ratio<br />

requires <strong>the</strong> development of a nuclear industry capable of reprocessing*fuel containing<br />

thorium and refabricating fuel containing 232U.<br />

loaded with approximately 3% enriched 235U comprises approximately 282 of <strong>the</strong> installed<br />

capacity, <strong>the</strong> FBR comprises 48%, and <strong>the</strong> LWR loaded with 11% 233U in 238U comprises 24%.<br />

Upon examining <strong>the</strong> flow of thorium and uranium metal associated with <strong>the</strong>se reactors, it<br />

can be seen that 38% of <strong>the</strong> reprocessing capacity must be capable of handling fuel con-<br />

taining thorium and 27% of <strong>the</strong> fabrication industry must be capable of handling fuel<br />

containing 2321).<br />

In this option in <strong>the</strong> year 2035, <strong>the</strong> LWR<br />

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L<br />

L<br />

L<br />

I '<br />

-ii-<br />

L<br />

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