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ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site

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............. .<br />

. .. .<br />

.=w as SSm, Amore attractive isotopic mixture would exist early in <strong>the</strong><br />

95<br />

plant lifetime (e.g., after one year of operation), but <strong>the</strong> total inven-<br />

tory WQUM be nueh smaller - only 86 kg oi 23%u =+ 24bpu with 13 kg of<br />

24(4Pu + 2%u,<br />

ho<strong>the</strong>r potential source of SSNM in a DMSR would be 233~a. T~FS nu-<br />

clide would have its maximum inventory of -63 kg early in <strong>the</strong> reactor<br />

life and slowly decllbne to about 41 kg at <strong>the</strong> end of life, In principle,<br />

this nuclide, if it could be cleaga~y and rapidly separated from <strong>the</strong> res%:<br />

of <strong>the</strong> fuel salt, could provide an equivalent amount of high-purity 23%<br />

through simple radioactive decay.<br />

3.%,2 Accessibility sf SSMM<br />

A major consideration regarding <strong>the</strong> accessibility of various foms<br />

of potential SSm in a DMSR is that all <strong>the</strong> materials are intimately mixed<br />

with -350 Mg of highly radioactive fuel salt with no known method for<br />

simple physical separation.<br />

nus, diversion of only a modest amount (a<br />

few kilograms of SSNM without plans for isotopic enriebent would require<br />

<strong>the</strong> removal of a number of tons of fuel salt from <strong>the</strong> reactor system. The<br />

need for such large (and o<strong>the</strong>rwise unjustifiable) salt removals, which<br />

without rep~lacenent would shut d ~ m <strong>the</strong> reactor, couple$ with <strong>the</strong> need for<br />

an elaborate chemical treatment facility to isolate <strong>the</strong> produet appears<br />

to make this approach relatively impractical.<br />

In princfpal, pure 233U could be diverted via <strong>the</strong> 233Pa route by<br />

modifying <strong>the</strong> in-plant hydrofluorinator to permit ita use as a fluori-<br />

nator. This would requlre two fluorinations of each batch of salt, with<br />

one occurring immediately after removal of <strong>the</strong> salt from <strong>the</strong> reactor to<br />

strip out <strong>the</strong> denatured uranium and a second about two months later to<br />

recover <strong>the</strong> 233U produced by 233Pa decay. However, i f <strong>the</strong> system were<br />

originally designed to handle batches si salt no larger than -1 m3, <strong>the</strong><br />

~ ~<br />

* Presumably, this approach would be rased only to divert plutonium<br />

~ _ ~ _ _<br />

because uranium diversion wou~d<br />

require isotopic enricbent and 23 +a<br />

diversion would encounter serious timing problems, as well as requiring<br />

<strong>the</strong> handling of more salt.<br />

Jk

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