Kilogram-scale purification of americium by ion exchange

Sequential anion and cation exchange processes have been used for the final purification of 241Am recovered during the reprocessing of aged plutonium metallurgical scrap. Plutonium was removed by absorption of Dowex 1, X-3.5 (30 to 50 mesh) anion exchange resin from 6.5 to 7.5 M HNO3 feed solution. Following a water dilution to 0.75 to 1.0 M HNO3, americium was absorbed on Dowex 50W, X-8 (50 to 100 mesh) cation exchange resion. Final purification was accomplished by elution of the absorbed band down 3 to 4 successive beds of the same resin, preloaded with Zn2+, with an NH4OH buffered chelating agent. The recovery of mixed 241Am-243Am from power reactor reprocessing waste has been demonstrated. Solvent extraction was used to recover a HNO3 solution of mixed lanthanides and actinides from waste generated by the reprocessng of 13.5 tons of Shippingport Power Reactor blanket fuel. Sequential cation exchange band-displacement processes were then used to separate americium and curium from the lanthanides and then to separate approx. 60 g of 244Cm from 1000 g of mixed 241Am-243Am