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

Abstract

A method for decontaminating uranium product from the Purex process comprises addition of hydrazine to the product uranyl nitrate stream from the Purex process, which contains hexavalent (UO.sub.2.sup.2+) uranium and heptavalent technetium (TcO.sub.4 -). Technetium in the product stream is reduced and then complexed by the addition of oxalic acid (H.sub.2 C.sub.2 O.sub.4), and the Tc-oxalate complex is readily separated from the uranium by solvent extraction with 30 vol. % tributyl phosphate in n-dodecane.

Inventors:
 [1]
  1. (Oak Ridge, TN)
Issue Date:
Research Org.:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN
OSTI Identifier:
865509
Patent Number(s):
4528165
Assignee:
United States of America as represented by United States (Washington, DC) ORNL
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
separation; uranium; technetium; recovery; spent; nuclear; fuel; method; decontaminating; product; purex; process; comprises; addition; hydrazine; uranyl; nitrate; stream; contains; hexavalent; uo; heptavalent; tco; reduced; complexed; oxalic; acid; tc-oxalate; complex; readily; separated; solvent; extraction; 30; vol; tributyl; phosphate; n-dodecane; readily separated; purex process; uranyl nitrate; oxalic acid; tributyl phosphate; product stream; solvent extraction; nuclear fuel; spent nuclear; process comprises; uranium product; solvent extract; /423/976/

Citation Formats

Friedman, Horace A. Separation of uranium from technetium in recovery of spent nuclear fuel. United States: N. p., 1985. Web.
Friedman, Horace A. Separation of uranium from technetium in recovery of spent nuclear fuel. United States.
Friedman, Horace A. Tue . "Separation of uranium from technetium in recovery of spent nuclear fuel". United States. https://www.osti.gov/servlets/purl/865509.
@article{osti_865509,
title = {Separation of uranium from technetium in recovery of spent nuclear fuel},
author = {Friedman, Horace A.},
abstractNote = {A method for decontaminating uranium product from the Purex process comprises addition of hydrazine to the product uranyl nitrate stream from the Purex process, which contains hexavalent (UO.sub.2.sup.2+) uranium and heptavalent technetium (TcO.sub.4 -). Technetium in the product stream is reduced and then complexed by the addition of oxalic acid (H.sub.2 C.sub.2 O.sub.4), and the Tc-oxalate complex is readily separated from the uranium by solvent extraction with 30 vol. % tributyl phosphate in n-dodecane.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1985},
month = {1}
}

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