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Title: Salt transport extraction of transuranium elements from lwr fuel

Abstract

A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl.sub.2 and a Cu--Mg alloy containing not less than about 25% by weight Mg at a temperature in the range of from about 750.degree. C. to about 850.degree. C. to precipitate uranium metal and some of the noble metal fission products leaving the Cu--Mg alloy having transuranium actinide metals and rare earth fission product metals and some of the noble metal fission products dissolved therein. The CaCl.sub.2 having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein is separated and electrolytically treated with a carbon electrode to reduce the CaO to Ca metal while converting the carbon electrode to CO and CO.sub.2. The Ca metal and CaCl.sub.2 is recycled to reduce additional oxide fuel. The Cu--Mg alloy having transuranium metals and rare earth fission product metals and the noble metal fission products dissolved therein is contacted with a transport salt including Mg Cl.sub.2 to transfer Mg values from the transport salt to the Cu--Mg alloy whilemore » transuranium actinide and rare earth fission product metals transfer from the Cu--Mg alloy to the transport salt. Then the transport salt is mixed with a Mg--Zn alloy to transfer Mg values from the alloy to the transport salt while the transuranium actinide and rare earth fission product values dissolved in the salt are reduced and transferred to the Mg--Zn alloy.« less

Inventors:
 [1];  [2];  [3];  [4];  [1]
  1. Naperville, IL
  2. Downers Grove, IL
  3. Oak Forest, IL
  4. Wheaton, IL
Issue Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
OSTI Identifier:
868523
Patent Number(s):
5160367
Assignee:
United States of America as represented by United States (Washington, DC)
Patent Classifications (CPCs):
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
DOE Contract Number:  
W-31109-ENG-38
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
salt; transport; extraction; transuranium; elements; lwr; fuel; process; separating; actinide; values; uranium; spent; nuclear; oxide; fuels; contain; rare; earth; noble; metal; fission; products; reduced; presence; cacl; cu-mg; alloy; containing; 25; weight; mg; temperature; range; 750; degree; 850; precipitate; leaving; metals; product; dissolved; therein; cao; alkali; iodine; separated; electrolytically; treated; carbon; electrode; reduce; converting; recycled; additional; contacted; including; transfer; mixed; mg-zn; transferred; alkali earth; salt including; carbon electrode; actinide values; dissolved therein; alloy containing; fission product; fission products; alkali metal; oxide fuel; rare earth; spent nuclear; noble metal; earth metal; alkali metals; uranium metal; earth metals; product values; earth fission; product metals; actinide metals; actinide metal; uranium values; transuranium actinide; metal fission; separating transuranium; transuranium elements; product metal; oxide fuels; nuclear oxide; lwr fuel; iodine dissolved; transport extraction; contain rare; /75/423/

Citation Formats

Pierce, R Dean, Ackerman, John P, Battles, James E, Johnson, Terry R, and Miller, William E. Salt transport extraction of transuranium elements from lwr fuel. United States: N. p., 1992. Web.
Pierce, R Dean, Ackerman, John P, Battles, James E, Johnson, Terry R, & Miller, William E. Salt transport extraction of transuranium elements from lwr fuel. United States.
Pierce, R Dean, Ackerman, John P, Battles, James E, Johnson, Terry R, and Miller, William E. Wed . "Salt transport extraction of transuranium elements from lwr fuel". United States. https://www.osti.gov/servlets/purl/868523.
@article{osti_868523,
title = {Salt transport extraction of transuranium elements from lwr fuel},
author = {Pierce, R Dean and Ackerman, John P and Battles, James E and Johnson, Terry R and Miller, William E},
abstractNote = {A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl.sub.2 and a Cu--Mg alloy containing not less than about 25% by weight Mg at a temperature in the range of from about 750.degree. C. to about 850.degree. C. to precipitate uranium metal and some of the noble metal fission products leaving the Cu--Mg alloy having transuranium actinide metals and rare earth fission product metals and some of the noble metal fission products dissolved therein. The CaCl.sub.2 having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein is separated and electrolytically treated with a carbon electrode to reduce the CaO to Ca metal while converting the carbon electrode to CO and CO.sub.2. The Ca metal and CaCl.sub.2 is recycled to reduce additional oxide fuel. The Cu--Mg alloy having transuranium metals and rare earth fission product metals and the noble metal fission products dissolved therein is contacted with a transport salt including Mg Cl.sub.2 to transfer Mg values from the transport salt to the Cu--Mg alloy while transuranium actinide and rare earth fission product metals transfer from the Cu--Mg alloy to the transport salt. Then the transport salt is mixed with a Mg--Zn alloy to transfer Mg values from the alloy to the transport salt while the transuranium actinide and rare earth fission product values dissolved in the salt are reduced and transferred to the Mg--Zn alloy.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1992},
month = {1}
}

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