Procedure 9a. Separation of Plutonium from Irradiated Uranium

The Pu. U and fission products are adsorbed on a cation exchange column from 0.3-0.5 M HNOg and washed with 0.5 M HNOg. The U and fission products are then eluted with 2.0 M HCl, and the Pu is stripped with 8M HCl. The Pu is then adsorbed onto anion exchange resin, washed with 8 M HCl, and finally stripped with 2 M HCl. 

5 ml of stock solution (containing about 15 /ug Pu), 5 ml of 4.0 M HNOg and 5 ml of 1.0 M NaNO were mixed in a flask, and made up to a volume of 50 ml with water. 02 reduces Pu(VI) to Pu(lV). Care has to be taken that concentration of HNOg is not allowed to fall below 0,1 M, since Pu then will hydrolyse and consequently coagulate on the column. 

This solution was adsorbed on Dowex 50 (140-160 mesh) and the column was washed with 0.5 M HNOg. Then 2.0 M HCl was applied to elute U and accompanying fission products. The washing with 2.0 M HCl was continued until the -activity was close to background. 

Pu and remaining fission products were eluted with 8 M HCl, a small amount of concentrated HNO + some NaNOg added (to oxidize Pu(III) to Pu(IV)), and this fraction was transferred to another column containing Dowex 1 (50-100 mesh), which beforehand had been washed with concentrated HCl containing a little concentrated HNO3. 

After the sorption step, the column was washed with 8 M HCl (containing a little concentrated HNOg) until the effluent was practically free from -activity. 

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Procedure 9a. Separation of Plutonium from Irradiated Uranium R. O. Lingjaerde (Ref. 255)... 

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