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}
}
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