Solvent wash solution

Compositions – Radioactive compositions – Nuclear reactor fuel

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210682, 252627, 423 8, 423 10, G21F 904, B01D 1100, B01D 1104

Patent

active

045955298

ABSTRACT:
Process for removing diluent degradation products from a solvent extraction solution, which has been used to recover uranium and plutonium from spent nuclear fuel. A wash solution and the solvent extraction solution are combined. The wash solution contains (a) water and (b) up to about, and including, 50 volume percent of at least one-polar water-miscible organic solvent based on the total volume of the water and the highly-polar organic solvent. The wash solution also preferably contains at least one inorganic salt. The diluent degradation products dissolve in the highly-polar organic solvent and the organic solvent extraction solvent do not dissolve in the highly-polar organic solvent. The highly-polar organic solvent and the extraction solvent are separated.

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McKibben, J. 1983, Chemistry of the Purex Process, Report #DPSPU-83-172-1, merican Chemical Society.

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