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Title: Plutonium recovery from organic materials

Abstract

A method is described for removing plutonium or the like from organic material wherein the organic material is leached with a solution containing a strong reducing agent such as titanium (III) (Ti/sup +3None)/, chromium (II) (Cr/ sup +2/), vanadium (II) (V/sup +2/) ions, or ferrous ethylenediaminetetraacetate (EDTA), the leaching yielding a plutonium-containing solution that is further processed to recover plutonium. The leach solution may also contain citrate or tartrate ion. (Official Gazette)

Inventors:
;
Publication Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4346865
Patent Number(s):
US 3778497
Assignee:
to United States Atomic Energy Commission
NSA Number:
NSA-29-026755
Resource Type:
Patent
Resource Relation:
Patent File Date: 1972 Jul 28; Other Information: C01f13/00. Orig. Receipt Date: 30-JUN-74
Country of Publication:
United States
Language:
English
Subject:
N40430* -Chemistry-Radiochemistry & Nuclear Chemistry- Radioactive Waste Treatment; *PLUTONIUM- SEPARATION PROCESSES; CELLULOSE; CHROMIUM COMPOUNDS; HYDROCARBONS; IRON COMPOUNDS; LEACHING; POLYETHYLENES; RADIOACTIVE WASTE PROCESSING; REDUCTION; TITANIUM COMPOUNDS; VANADIUM COMPOUNDS

Citation Formats

Deaton, R L, and Silver, G L. Plutonium recovery from organic materials. United States: N. p., 1973. Web.
Deaton, R L, & Silver, G L. Plutonium recovery from organic materials. United States.
Deaton, R L, and Silver, G L. 1973. "Plutonium recovery from organic materials". United States.
@article{osti_4346865,
title = {Plutonium recovery from organic materials},
author = {Deaton, R L and Silver, G L},
abstractNote = {A method is described for removing plutonium or the like from organic material wherein the organic material is leached with a solution containing a strong reducing agent such as titanium (III) (Ti/sup +3None)/, chromium (II) (Cr/ sup +2/), vanadium (II) (V/sup +2/) ions, or ferrous ethylenediaminetetraacetate (EDTA), the leaching yielding a plutonium-containing solution that is further processed to recover plutonium. The leach solution may also contain citrate or tartrate ion. (Official Gazette)},
doi = {},
url = {https://www.osti.gov/biblio/4346865}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Dec 11 00:00:00 EST 1973},
month = {Tue Dec 11 00:00:00 EST 1973}
}