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Title: Recovery of americium-241 from aged plutonium. [Process involves dissolution, complexation with aluminium, solvent extraction, ion exchange chromatography and precipitation]

Abstract

A process was developed for recovering /sup 241/Am from aged plutonium oxide. The oxide is dissolved with nitric acid and fluoride, the fluoride is complexed with aluminum, and plutonium and americium are separated by one cycle of solvent extraction. Americium is concentrated and purified by cation exchange chromatography and precipitated as oxalate. The process was successfully operated in Savannah River Plant facilities to recover approximately 720 g of /sup 241/Am from about 60 kg of aged plutonium oxide.

Authors:
; ;
Publication Date:
Research Org.:
Du Pont de Nemours (E.I.) and Co., Aiken, S.C. (USA). Savannah River Lab.
OSTI Identifier:
7334971
Report Number(s):
DP-1419
TRN: 77-000053
DOE Contract Number:  
E(07-2)-1
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 37 INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; AMERICIUM 241; SEPARATION PROCESSES; ION EXCHANGE CHROMATOGRAPHY; NITRIC ACID; PLUTONIUM OXIDES; PRECIPITATION; SOLVENT EXTRACTION; ACTINIDE COMPOUNDS; ACTINIDE ISOTOPES; ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; AMERICIUM ISOTOPES; CHALCOGENIDES; CHROMATOGRAPHY; EXTRACTION; HEAVY NUCLEI; HYDROGEN COMPOUNDS; INORGANIC ACIDS; ISOTOPES; NUCLEI; ODD-EVEN NUCLEI; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; RADIOISOTOPES; TRANSURANIUM COMPOUNDS; YEARS LIVING RADIOISOTOPES; 052001* - Nuclear Fuels- Waste Processing; 400105 - Separation Procedures

Citation Formats

Burney, G. A., Harmon, H. D., and Hyder, M. L. Recovery of americium-241 from aged plutonium. [Process involves dissolution, complexation with aluminium, solvent extraction, ion exchange chromatography and precipitation]. United States: N. p., 1976. Web. doi:10.2172/7334971.
Burney, G. A., Harmon, H. D., & Hyder, M. L. Recovery of americium-241 from aged plutonium. [Process involves dissolution, complexation with aluminium, solvent extraction, ion exchange chromatography and precipitation]. United States. https://doi.org/10.2172/7334971
Burney, G. A., Harmon, H. D., and Hyder, M. L. Thu . "Recovery of americium-241 from aged plutonium. [Process involves dissolution, complexation with aluminium, solvent extraction, ion exchange chromatography and precipitation]". United States. https://doi.org/10.2172/7334971. https://www.osti.gov/servlets/purl/7334971.
@article{osti_7334971,
title = {Recovery of americium-241 from aged plutonium. [Process involves dissolution, complexation with aluminium, solvent extraction, ion exchange chromatography and precipitation]},
author = {Burney, G. A. and Harmon, H. D. and Hyder, M. L.},
abstractNote = {A process was developed for recovering /sup 241/Am from aged plutonium oxide. The oxide is dissolved with nitric acid and fluoride, the fluoride is complexed with aluminum, and plutonium and americium are separated by one cycle of solvent extraction. Americium is concentrated and purified by cation exchange chromatography and precipitated as oxalate. The process was successfully operated in Savannah River Plant facilities to recover approximately 720 g of /sup 241/Am from about 60 kg of aged plutonium oxide.},
doi = {10.2172/7334971},
url = {https://www.osti.gov/biblio/7334971}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1976},
month = {7}
}