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Title: Magnesium 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 U-Fe alloy containing not less than about 84% by weight uranium at a temperature in the range of from about 800.degree. C. to about 850.degree. C. to produce additional uranium metal which dissolves in the U-Fe alloy raising the uranium concentration and having transuranium actinide metals and rare earth fission product metals and 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 U-Fe alloy having transuranium actinide metals and rare earth fission product metals and the noble metal fission products dissolved therein is contacted with Mg metal which takes up the actinide and rare earth fission product metals. The U-Fe alloy retains the noble metalmore » fission products and is stored while the Mg is distilled and recycled leaving the transuranium actinide and rare earth fission products isolated.« less

Inventors:
 [1];  [2];  [3];  [4];  [4]
  1. Downers Grove, IL
  2. Oak Forest, IL
  3. Wheaton, IL
  4. Naperville, IL
Issue Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
OSTI Identifier:
868466
Patent Number(s):
5147616
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:
magnesium; 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; u-fe; alloy; containing; 84; weight; temperature; range; 800; degree; 850; produce; additional; dissolves; raising; concentration; metals; product; dissolved; therein; cao; alkali; iodine; separated; electrolytically; treated; carbon; electrode; reduce; converting; recycled; contacted; mg; takes; retains; stored; distilled; leaving; isolated; alkali earth; 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; earth fission; product metals; actinide metals; actinide metal; uranium values; transuranium actinide; metal fission; separating transuranium; transuranium elements; product metal; oxide fuels; nuclear oxide; produce additional; lwr fuel; iodine dissolved; transport extraction; contain rare; /423/75/205/

Citation Formats

Ackerman, John P, Battles, James E, Johnson, Terry R, Miller, William E, and Pierce, R Dean. Magnesium transport extraction of transuranium elements from LWR fuel. United States: N. p., 1992. Web.
Ackerman, John P, Battles, James E, Johnson, Terry R, Miller, William E, & Pierce, R Dean. Magnesium transport extraction of transuranium elements from LWR fuel. United States.
Ackerman, John P, Battles, James E, Johnson, Terry R, Miller, William E, and Pierce, R Dean. Wed . "Magnesium transport extraction of transuranium elements from LWR fuel". United States. https://www.osti.gov/servlets/purl/868466.
@article{osti_868466,
title = {Magnesium transport extraction of transuranium elements from LWR fuel},
author = {Ackerman, John P and Battles, James E and Johnson, Terry R and Miller, William E and Pierce, R Dean},
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 U-Fe alloy containing not less than about 84% by weight uranium at a temperature in the range of from about 800.degree. C. to about 850.degree. C. to produce additional uranium metal which dissolves in the U-Fe alloy raising the uranium concentration and having transuranium actinide metals and rare earth fission product metals and 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 U-Fe alloy having transuranium actinide metals and rare earth fission product metals and the noble metal fission products dissolved therein is contacted with Mg metal which takes up the actinide and rare earth fission product metals. The U-Fe alloy retains the noble metal fission products and is stored while the Mg is distilled and recycled leaving the transuranium actinide and rare earth fission products isolated.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1992},
month = {1}
}

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