C - Chemistry – Metallurgy – 22 – B
Patent
C - Chemistry, Metallurgy
22
B
53/190
C22B 60/02 (2006.01) C01F 17/00 (2006.01) C01G 56/00 (2006.01) C22B 3/32 (2006.01) C22B 3/38 (2006.01) G21C 19/46 (2006.01) G21F 9/00 (2006.01)
Patent
CA 1097925
ABSTRACT OF THE INVENTION A process for partitioning and recovering actinide values from acidic waste solutions resulting from reprocessing of irradiated nuclear fuels by adding hydroxylammonium nitrate and hydrazine to the waste solution to adjust the valence of the neptunium and plutonium values in the solution to the +4 oxidation state, thus forming a feed solution and contacting the feed solution with an extractant of di-hexoxyethyl phosphoric acid in an organic diluent whereby the actinide values, most of the rare earth values and some fission product values are taken up by the extractant. Separation is achieved by contacting the loaded extractant with two aqueous strip solutions, a nitric acid solution to selectively strip the americium, curium and rare earth values and an oxalate solution of tetramethylammonium hydrogen oxalate and oxalic acid or trimethylammonium hydrogen oxalate to selectively strip the neptunium, plutonium and fission product values. Uranium values remain in the extractant and may be recovered with a phosphoric acid strip. The neptunium and plutonium values are recovered from the oxalate by adding sufficient nitric acid to destroy the complexing ability of the oxalate, forming a second feed, and contacting the second feed with a second extractant of tricaprylmethylammonlum nitrate in an inert diluent whereby the neptunium and plutonium values are selectively extracted. The values are recovered from the extractant with formic acid.
318798
Delphin Walter H.
Horwitz E. Philip
Mason George W.
Meredith & Finlayson
United States Of America (government Of The) United States Depar
LandOfFree
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