ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site
ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site
ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site
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+<br />
o=<br />
$5<br />
56<br />
c < 2.5<br />
w-<br />
1-<br />
m"<br />
4<br />
-<br />
30<br />
<strong>ORNL</strong>-DWG 804266 ETD<br />
FIRST FUEL<br />
4<br />
5 0.0<br />
0 1 2 3<br />
OPERATING TIME (yri<br />
4 5<br />
Fig. 5. Time variation of core reactivity in a once-through BMSR<br />
operating at 75% capacity factor.<br />
no<br />
OHNL -DVG 80-4267 FVD<br />
I I I<br />
1 0 20 30<br />
OPERATING TIME (vr)<br />
Fig. 4. Conversion ratio vs time,<br />
makeup fuel. The lifestme average conversion ratio for <strong>the</strong> 30-year fuel<br />
cycle is ekose to 0.8.<br />
The schedule of fuel additions, including <strong>the</strong> initial critical load-<br />
ing for a 1-GWe plant operating at a 75% capacity factor is shown in Table<br />
17. This table also includes <strong>the</strong> quantities of <strong>the</strong> U308 and separative<br />
work required to supply <strong>the</strong> fissile materialie ~hus, <strong>the</strong> lifetime re-<br />
quirement would be about 2688 tons of U308 i f m credit were allowed for<br />
<strong>the</strong> end-of-life fissile in~entory. However, uranium is readily r&coV~B"-<br />
able from this fuel in a pure and reusable fom as LEge The recovered<br />
uranium would have to be reenriched, ei<strong>the</strong>r by isotopic separation or by<br />
addition of high-enrichment fuel, before it could be reused in ano<strong>the</strong>r<br />
DMSR, but reuse in some manner might be preferable to discarding <strong>the</strong>