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Procedure 9b. Separation of Plutonium from Uranium Metal

This procedure makes use of the co-precipitation properties of the different oxidation states of Pu on BiPO. The Pu is first oxidized to Pu(VI) which does not carry on BiPO, and then reduced to Pu(IV) which carries. An additional purification step is provided by extraction into TTA. Yield is greater than 60%. [Pg.130]

The solution is diluted to 3 M in HNO and solid NaBiOg is added to oxidize Pu to the +6 valency state. [Pg.130]

The solution is made 0.1 in HNOg (if it becomes turbid, HNOg is added until the solution is clear) and 0.1 M in phosphate. The BiPO precipitate is centrifuged off. This precipitate carries most of the fission products, and especially those with a chemistry similar to Pu(IV). [Pg.130]

Bi is then added (1 drop 0.1 M Bi for each ml solution) to precipitate BiPO, which carries all the Pu. The precipitate, which is usually contaminated with some U is centrifuged off and washed. [Pg.130]

The phosphates in the precipitate are converted into hydroxides by treating with warm 10 M KOH. After centrifuging the solution is drawn- off. and the precipitate is washed and dissolved in hot cone. HNOg. [Pg.130]


Procedure 9b, Separation of Plutonium from Uranium Metal. J. Rydberg (Ref. 341) Outline of Method... [Pg.130]




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