skip to main content
DOE Patents title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: 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 Lab., TN (USA)
OSTI Identifier:
6656147
Patent Number(s):
-US-A6018550
Application Number:
ON: DE89000096
Assignee:
Dept. of Energy TIC; ERA-14-004183; EDB-89-000981
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 = {1987},
month = {2}
}