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Title: Salt transport extraction of transuranium elements from LWR fuel

Abstract

A process is described for 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 C to about 850 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 MgCl[sub 2] to transfer Mg values from the transportmore » 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. 2 figs.« less

Inventors:
; ; ; ;
Issue Date:
OSTI Identifier:
7235994
Patent Number(s):
5160367 A
Application Number:
PPN: US 7-770385
Assignee:
Dept. of Energy, Washington, DC (United States) PTO; EDB-94-086695
DOE Contract Number:  
W-31109-ENG-38
Resource Type:
Patent
Resource Relation:
Patent File Date: 3 Oct 1991
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; SPENT FUELS; REPROCESSING; TRANSURANIUM ELEMENTS; SEPARATION PROCESSES; URANIUM; PRECIPITATION; CALCIUM; CALCIUM CHLORIDES; COPPER ALLOYS; DISSOLUTION; ELECTROLYSIS; MAGNESIUM ALLOYS; REDUCTION; URANIUM OXIDES; ZINC ALLOYS; ACTINIDE COMPOUNDS; ACTINIDES; ALKALINE EARTH METAL COMPOUNDS; ALKALINE EARTH METALS; ALLOYS; CALCIUM COMPOUNDS; CALCIUM HALIDES; CHALCOGENIDES; CHEMICAL REACTIONS; CHLORIDES; CHLORINE COMPOUNDS; ELEMENTS; ENERGY SOURCES; FUELS; HALIDES; HALOGEN COMPOUNDS; LYSIS; MATERIALS; METALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; REACTOR MATERIALS; URANIUM COMPOUNDS; 050800* - Nuclear Fuels- Spent Fuels Reprocessing

Citation Formats

Pierce, R.D., Ackerman, J.P., Battles, J.E., Johnson, T.R., and Miller, W.E. Salt transport extraction of transuranium elements from LWR fuel. United States: N. p., 1992. Web.
Pierce, R.D., Ackerman, J.P., Battles, J.E., Johnson, T.R., & Miller, W.E. Salt transport extraction of transuranium elements from LWR fuel. United States.
Pierce, R.D., Ackerman, J.P., Battles, J.E., Johnson, T.R., and Miller, W.E. Tue . "Salt transport extraction of transuranium elements from LWR fuel". United States.
@article{osti_7235994,
title = {Salt transport extraction of transuranium elements from LWR fuel},
author = {Pierce, R.D. and Ackerman, J.P. and Battles, J.E. and Johnson, T.R. and Miller, W.E.},
abstractNote = {A process is described for 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 C to about 850 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 MgCl[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. 2 figs.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1992},
month = {11}
}