Method of separating and recovering uranium and related cations from spent Purex-type systems
Abstract
A process for separating uranium and related cations from a spent Purex-type solvent extraction system which contains degradation complexes of tributylphosphate wherein the system is subjected to an ion-exchange process prior to a sodium carbonate scrubbing step. A further embodiment comprises recovery of the separated uranium and related cations. 5 figs.
- Inventors:
- Issue Date:
- Research Org.:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- OSTI Identifier:
- 6656147
- Patent Number(s):
- 6018550
- Application Number:
- ON: DE89000096
- Assignee:
- Dept. of Energy
- Patent Classifications (CPCs):
-
H - ELECTRICITY H04 - ELECTRIC COMMUNICATION TECHNIQUE H04L - TRANSMISSION OF DIGITAL INFORMATION, e.g. TELEGRAPHIC COMMUNICATION
- DOE Contract Number:
- AC05-84OR21400
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CATIONS; SEPARATION PROCESSES; URANIUM; INVENTIONS; PUREX PROCESS; RECOVERY; REPROCESSING; SCRUBBING; SODIUM CARBONATES; SOLVENT EXTRACTION; SPENT FUELS; ACTINIDES; ALKALI METAL COMPOUNDS; CARBON COMPOUNDS; CARBONATES; CHARGED PARTICLES; ELEMENTS; ENERGY SOURCES; EXTRACTION; FUELS; IONS; MATERIALS; METALS; NUCLEAR FUELS; OXYGEN COMPOUNDS; REACTOR MATERIALS; SODIUM COMPOUNDS; 050800* - Nuclear Fuels- Spent Fuels Reprocessing
Citation Formats
Mailen, J C, and Tallent, O K. Method of separating and recovering uranium and related cations from spent Purex-type systems. United States: N. p., 1987.
Web.
Mailen, J C, & Tallent, O K. Method of separating and recovering uranium and related cations from spent Purex-type systems. United States.
Mailen, J C, and Tallent, O K. Wed .
"Method of separating and recovering uranium and related cations from spent Purex-type systems". United States.
@article{osti_6656147,
title = {Method of separating and recovering uranium and related cations from spent Purex-type systems},
author = {Mailen, J C and Tallent, O K},
abstractNote = {A process for separating uranium and related cations from a spent Purex-type solvent extraction system which contains degradation complexes of tributylphosphate wherein the system is subjected to an ion-exchange process prior to a sodium carbonate scrubbing step. A further embodiment comprises recovery of the separated uranium and related cations. 5 figs.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Feb 25 00:00:00 EST 1987},
month = {Wed Feb 25 00:00:00 EST 1987}
}
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