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ORNL-1816 - the Molten Salt Energy Technologies Web Site

ORNL-1816 - the Molten Salt Energy Technologies Web Site

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fused salt bath to permit dissolution at a pene-<br />

tration rate of 22 to 35 milshr, passage of <strong>the</strong><br />

UF,-F, mixture through a bed of NaF at 650OC to<br />

obtain additional decontamination, and final puri-<br />

fication of <strong>the</strong> UF, by distillation.<br />

140<br />

Recovery of <strong>the</strong> uranium by fluoride volatilization<br />

will be easy, although methods for obtaining a<br />

decontamination factor of about 10, will have to be<br />

developed in order to allow metallurgical pro-<br />

cessing of <strong>the</strong> uranium.<br />

.b<br />

c

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