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

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

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esponsibility for a chemical processing facility, <strong>the</strong> sociopolitical ac-<br />

ceptability of colocating such a facility with each DMSR, and <strong>the</strong> Picens-<br />

ing questions that way arise from such an arrangement.<br />

The ~<strong>the</strong>r end of <strong>the</strong> rartge of possible fuel cycle performances for<br />

DMSRs is represented by <strong>the</strong> 38-year cycle descrfbed earlier in this report<br />

as <strong>the</strong> reference concept.<br />

Although this system, with a lifetime require-<br />

ment of 1860 Mg (2000 short tons) of U308, would be <strong>the</strong> largest consumer<br />

of natural UK~R~UITI and separative work among <strong>the</strong> DMSR opti~ns considered,<br />

it still wuuld require substantially less of <strong>the</strong>se commodities than <strong>the</strong><br />

once-through fuel cycle in light-water reactors. In <strong>the</strong> absence of fa-<br />

cilities for recycling <strong>the</strong> won-SIW constituents of <strong>the</strong> fuel salt, this<br />

approach would use less of such materials than any of <strong>the</strong> o<strong>the</strong>r alterna-<br />

tives. However, despite <strong>the</strong> 38-year fuel cycle, this concept would not<br />

eliminate all on-site chemical treatment uf <strong>the</strong> fuel salt. Tlne activities<br />

to maintain <strong>the</strong> desired u3+/u4+ ratis in <strong>the</strong> fuel ana <strong>the</strong> treatments to<br />

limit <strong>the</strong> level of oxide contamination in <strong>the</strong> salt would still be needed.<br />

Thus, even <strong>the</strong> "sFmpPest" DMSW would require SQIW equipment for and some<br />

technical competence in chemical processing, even though nei<strong>the</strong>r would<br />

directly iRVQlVe <strong>the</strong> sm ill <strong>the</strong> system.<br />

The intermediate concepts that make use of a shorter salt discard<br />

cycle merely substitute consumption of o<strong>the</strong>r fluoride salts for past of<br />

<strong>the</strong> fissile uranium consumption in <strong>the</strong> reference 30-year cycle, Because<br />

<strong>the</strong>se o<strong>the</strong>r fluorides (especialby 'Lip> may also be relatively expensive<br />

this substitution might not always be cost effective. In addition, any<br />

system that used salt discard would have to recover uranium from <strong>the</strong><br />

"wa~te'~ salt to prevent excessive uranium consumption. This would add<br />

yet ano<strong>the</strong>r chemical processing operation to <strong>the</strong> reactor plant.<br />

The alternatives that rely on special treatment schemes to remove<br />

flssion products from <strong>the</strong> fuel salt may have attractive fuel. utilization<br />

characteristics, but <strong>the</strong>y have not been analyzed in sufficient detail eo<br />

pernit an accurate characterization. In addition, considerable research<br />

and development would be required before such processes cou$d be shown to<br />

be technically feasible. Consequently, little incentive is apparent at<br />

this time to propose new and different chemical p ~ ~ e s sconcepts i ~ ~ g € 0 ~<br />

BMSRs 0

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