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Title: Kilogram-scale purification of americium by ion exchange

Conference ·
OSTI ID:5381944

Sequential anion and cation exchange processes have been used for the final purification of /sup 241/Am 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 HNO/sub 3/ feed solution. Following a water dilution to 0.75 to 1.0 M HNO/sub 3/, 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 Zn/sup 2 +/, with an NH/sub 4/OH buffered chelating agent. The recovery of mixed /sup 241/Am-/sup 243/Am from power reactor reprocessing waste has been demonstrated. Solvent extraction was used to recover a HNO/sub 3/ 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 /sup 244/Cm from 1000 g of mixed /sup 241/Am-/sup 243/Am.

Research Organization:
Battelle Pacific Northwest Labs., Richland, WA (USA)
DOE Contract Number:
EY-76-C-06-1830
OSTI ID:
5381944
Report Number(s):
PNL-SA-7844; CONF-7910108-4; TRN: 80-008413
Resource Relation:
Conference: Symposium on separation science and technology for energy applications, Gatlinburg, TN, USA, 30 Oct 1979
Country of Publication:
United States
Language:
English