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Title: ION EXCHANGE ADSORPTION PROCESS FOR PLUTONIUM SEPARATION

Abstract

Ion exchange processes for the separation of plutonium from fission products are described. In accordance with these processes an aqueous solution containing plutonium and fission products is contacted with a cation exchange resin under conditions favoring adsorption of plutonium and fission products on the resin. A portion of the fission product is then eluted with a solution containing 0.05 to 1% by weight of a carboxylic acid. Plutonium is next eluted with a solution containing 2 to 8 per cent by weight of the same carboxylic acid, and the remaining fission products on the resin are eluted with an aqueous solution containing over 10 per cent by weight of sodium bisulfate.

Inventors:
; ;
Issue Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4043050
Patent Number(s):
2992249
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-15-022382
NSA Number:
NSA-15-022382
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-61
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY

Citation Formats

Boyd, G.E., Russell, E.R., and Taylor, M.D. ION EXCHANGE ADSORPTION PROCESS FOR PLUTONIUM SEPARATION. United States: N. p., 1961. Web.
Boyd, G.E., Russell, E.R., & Taylor, M.D. ION EXCHANGE ADSORPTION PROCESS FOR PLUTONIUM SEPARATION. United States.
Boyd, G.E., Russell, E.R., and Taylor, M.D. Tue . "ION EXCHANGE ADSORPTION PROCESS FOR PLUTONIUM SEPARATION". United States.
@article{osti_4043050,
title = {ION EXCHANGE ADSORPTION PROCESS FOR PLUTONIUM SEPARATION},
author = {Boyd, G.E. and Russell, E.R. and Taylor, M.D.},
abstractNote = {Ion exchange processes for the separation of plutonium from fission products are described. In accordance with these processes an aqueous solution containing plutonium and fission products is contacted with a cation exchange resin under conditions favoring adsorption of plutonium and fission products on the resin. A portion of the fission product is then eluted with a solution containing 0.05 to 1% by weight of a carboxylic acid. Plutonium is next eluted with a solution containing 2 to 8 per cent by weight of the same carboxylic acid, and the remaining fission products on the resin are eluted with an aqueous solution containing over 10 per cent by weight of sodium bisulfate.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1961},
month = {7}
}