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

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:
 [1];  [1]
  1. (Knoxville, TN)
Issue Date:
Research Org.:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN
OSTI Identifier:
864964
Patent Number(s):
4443413
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; product; stream; purex; process; separated; contacting; aqueous; hydrazine; reduce; tc; therein; reduced; species; organic; phase; containing; tributyl; phosphate; diluent; extract; purex process; aqueous stream; tributyl phosphate; phase containing; product stream; organic phase; nuclear fuel; spent nuclear; /423/

Citation Formats

Pruett, David J., and McTaggart, Donald R. Separation of uranium from technetium in recovery of spent nuclear fuel. United States: N. p., 1984. Web.
Pruett, David J., & McTaggart, Donald R. Separation of uranium from technetium in recovery of spent nuclear fuel. United States.
Pruett, David J., and McTaggart, Donald R. Sun . "Separation of uranium from technetium in recovery of spent nuclear fuel". United States. https://www.osti.gov/servlets/purl/864964.
@article{osti_864964,
title = {Separation of uranium from technetium in recovery of spent nuclear fuel},
author = {Pruett, David J. and McTaggart, Donald 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 = {1984},
month = {1}
}

Patent:

Save / Share: