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Title: Separation of uranium from technetium in recovery of spent nuclear fuel

Abstract

Uranium and technetium in the product stream of the Purex process for recovery of uranium in spent nuclear fuel are separated by (1) contacting the aqueous Purex product stream with hydrazine to reduce Tc/sup +7/ therein to a reduced species, and (2) contacting said aqueous stream with an organic phase containing tributyl phosphate and an organic diluent to extract uranium from said aqueous stream into said organic phase.

Inventors:
;
Issue Date:
OSTI Identifier:
6982353
Application Number:
ON: DE84011306
Assignee:
Dept. of Energy ERA-09-025400; EDB-84-080636
DOE Contract Number:  
AC05-84OR21400
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 37 INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; TECHNETIUM; SEPARATION PROCESSES; URANIUM; SOLVENT EXTRACTION; PUREX PROCESS; SPENT FUELS; TBP; ACTINIDES; BUTYL PHOSPHATES; ELEMENTS; ENERGY SOURCES; ESTERS; EXTRACTION; FUELS; MATERIALS; METALS; NUCLEAR FUELS; ORGANIC COMPOUNDS; ORGANIC PHOSPHORUS COMPOUNDS; PHOSPHORIC ACID ESTERS; REACTOR MATERIALS; REPROCESSING; TRANSITION ELEMENTS; 050800* - Nuclear Fuels- Spent Fuels Reprocessing; 400105 - Separation Procedures

Citation Formats

Pruett, D.J., and McTaggart, D.R. Separation of uranium from technetium in recovery of spent nuclear fuel. United States: N. p., 1983. Web.
Pruett, D.J., & McTaggart, D.R. Separation of uranium from technetium in recovery of spent nuclear fuel. United States.
Pruett, D.J., and McTaggart, D.R. Wed . "Separation of uranium from technetium in recovery of spent nuclear fuel". United States.
@article{osti_6982353,
title = {Separation of uranium from technetium in recovery of spent nuclear fuel},
author = {Pruett, D.J. and McTaggart, D.R.},
abstractNote = {Uranium and technetium in the product stream of the Purex process for recovery of uranium in spent nuclear fuel are separated by (1) contacting the aqueous Purex product stream with hydrazine to reduce Tc/sup +7/ therein to a reduced species, and (2) contacting said aqueous stream with an organic phase containing tributyl phosphate and an organic diluent to extract uranium from said aqueous stream into said organic phase.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1983},
month = {8}
}