John T Ackerman

US Patent:

6911134, Jun 28, 2005

Filed:

Sep 6, 2002

Appl. No.:

10/236133

Inventors:

Dennis W. Dees - Downers Grove IL, US
John P. Ackerman - Downers Grove IL, US

Assignee:

The University of Chicago - Chicago IL

International Classification:

C25C005/04
C25C003/34

US Classification:

205 43, 205 47, 205354, 205363, 205367, 205368

Abstract:

A method of electrochemically reducing a metal oxide to the metal in an electrochemical cell is disclosed along with the cell. Each of the anode and cathode operate at their respective maximum reaction rates. An electrolyte and an anode at which oxygen can be evolved, and a cathode including a metal oxide to be reduced are included as is a third electrode with independent power supplies connecting the anode and the third electrode and the cathode and the third electrode.

US Patent:

7410561, Aug 12, 2008

Filed:

Mar 21, 2005

Appl. No.:

11/084940

Inventors:

Dennis W. Dees - Downers Groves IL, US
John P. Ackerman - Downers Grove IL, US

Assignee:

UChicago Argonne, LLC - Chicago IL

International Classification:

C25C 5/04
C25C 3/34

US Classification:

205 43, 205368, 2042307, 2042431

Abstract:

A method of electrochemically reducing a metal oxide to the metal in an electrochemical cell is disclosed along with the cell. Each of the anode and cathode operate at their respective maximum reaction rates. An electrolyte and an anode at which oxygen can be evolved, and a cathode including a metal oxide to be reduced are included as is a third electrode with independent power supplies connecting the anode and the third electrode and the cathode and the third electrode.

US Patent:

7638026, Dec 29, 2009

Filed:

Aug 24, 2005

Appl. No.:

11/215202

Inventors:

James L. Willit - Batavia IL, US
John P. Ackerman - Prescott AZ, US
Mark A. Williamson - Naperville IL, US

Assignee:

The United States of America as represented by the United States Department of Energy - Washington DC

International Classification:

C25C 3/34

US Classification:

205 47, 2042431, 204244, 204247, 205 43

Abstract:

This is a single stage process for treating spent nuclear fuel from light water reactors. The spent nuclear fuel, uranium oxide, UO, is added to a solution of UCldissolved in molten LiCl. A carbon anode and a metallic cathode is positioned in the molten salt bath. A power source is connected to the electrodes and a voltage greater than or equal to 1. 3 volts is applied to the bath. At the anode, the carbon is oxidized to form carbon dioxide and uranium chloride. At the cathode, uranium is electroplated. The uranium chloride at the cathode reacts with more uranium oxide to continue the reaction. The process may also be used with other transuranic oxides and rare earth metal oxides.

US Patent:

51603675, Nov 3, 1992

Filed:

Oct 3, 1991

Appl. No.:

7/770385

Inventors:

R. Dean Pierce - Naperville IL
John P. Ackerman - Downers Grove IL
James E. Battles - Oak Forest IL
Terry R. Johnson - Wheaton IL
William E. Miller - Naperville IL

Assignee:

The United States of America as represented by the United States
Department of Energy - Washington DC

International Classification:

C22B 6000

US Classification:

75397

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.

US Patent:

41156323, Sep 19, 1978

Filed:

May 5, 1977

Appl. No.:

5/794295

Inventors:

Kimio Kinoshita - Downers Grove IL
John P. Ackerman - Downers Grove IL

Assignee:

The United States of America as represented by the United States
Department of Energy - Washington DC

International Classification:

H01M 800
H01M 814

US Classification:

429188

Abstract:

An electrolyte compact for fuel cells includes a particulate support material of lithium aluminate that contains a mixture of alkali metal compounds, such as carbonates or hydroxides, as the active electrolyte material. The porous lithium aluminate support structure is formed by mixing alumina particles with a solution of lithium hydroxide and another alkali metal hydroxide, evaporating the solvent from the solution and heating to a temperature sufficient to react the lithium hydroxide with alumina to form lithium aluminate. Carbonates are formed by reacting the alkali metal hydroxides with carbon dioxide gas in an exothermic reaction which may proceed simultaneously with the formation with the lithium aluminate. The mixture of lithium aluminate and alkali metal in an electrolyte active material is pressed or otherwise processed to form the electrolyte structure for assembly into a fuel cell.

US Patent:

51417235, Aug 25, 1992

Filed:

Oct 3, 1991

Appl. No.:

7/770386

Inventors:

William E. Miller - Naperville IL
John P. Ackerman - Downers Grove IL
James E. Battles - Oak Forest IL
Terry R. Johnson - Wheaton IL
R. Dean Pierce - Naperville IL

Assignee:

The United States of America as represented by the United States
Department of Energy - Washington DC

International Classification:

C22B 6002

US Classification:

423 5

Abstract:

A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels containing rare earth and noble metal fission products as well as other fission products is disclosed. The oxide fuel is reduced with Ca metal in the presence of Ca chloride and a U-Fe alloy which is liquid at about 800. degree. C. to dissolve uranium metal and the noble metal fission product metals and transuranium actinide metals and rare earth fission product metals leaving Ca chloride having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein. The Ca chloride and CaO and the fission products contained therein are separated from the U-Fe alloy and the metal values dissolved therein. The U-Fe alloy having dissolved therein reduced metals from the spent nuclear fuel is contacted with a mixture of one or more alkali metal or alkaline earth metal halides selected from the class consisting of alkali metal or alkaline earth metal and Fe or U halide or a combination thereof to transfer transuranium actinide metals and rare earth metals to the halide salt leaving the uranium and some noble metal fission products in the U-Fe alloy and thereafter separating the halide salt and the transuranium metals dissolved therein from the U-Fe alloy and the metals dissolved therein.

US Patent:

50965450, Mar 17, 1992

Filed:

May 21, 1991

Appl. No.:

7/703641

Inventors:

John P. Ackerman - Downers Grove IL

Assignee:

The United States of America as represented by the United States
Department of Energy - Washington DC

International Classification:

C25C 334

US Classification:

204 15

Abstract:

A process for separating uranium values and transuranic values from fission products containing rare earth values when the values are contained together in a molten chloride salt electrolyte. A molten chloride salt electrolyte with a first ratio of plutonium chloride to uranium chloride is contacted with both a solid cathode and an anode having values of uranium and fission products including plutonium. A voltage is applied across the anode and cathode electrolytically to transfer uranium and plutonium from the anode to the electrolyte while uranium values in the electrolyte electrolytically deposit as uranium metal on the solid cathode in an amount equal to the uranium and plutonium transferred from the anode causing the electrolyte to have a second ratio of plutonium chloride to uranium chloride. Then the solid cathode with the uranium metal deposited thereon is removed and molten cadmium having uranium dissolved therein is brought into contact with the electrolyte resulting in chemical transfer of plutonium values from the electrolyte to the molten cadmium and transfer of uranium values from the molten cadmium to the electrolyte until the first ratio of plutonium chloride to uranium chloride is reestablished.

US Patent:

48805068, Nov 14, 1989

Filed:

Nov 5, 1987

Appl. No.:

7/117880

Inventors:

John P. Ackerman - Downers Grove IL
William E. Miller - Naperville IL

Assignee:

The United States of America as represented by the Department of Energy - Washington DC

International Classification:

C25C 334

US Classification:

204 15

Abstract:

An electrorefining process and apparatus for the recovery of uranium and a mixture of uranium and plutonium from spent fuel using an electrolytic cell having a lower molten cadmium pool containing spent nuclear fuel, an intermediate electrolyte pool, an anode basket containing spent fuel, and two cathodes, the first cathode composed of either a solid alloy or molten cadmium and the second cathode composed of molten cadmium. Using this cell, additional amounts of uranium and plutonium from the anode basket are dissolved in the lower molten cadmium pool, and then substantially pure uranium is electrolytically transported and deposited on the first alloy or molten cadmium cathode. Subsequently, a mixture of uranium and plutonium is electrotransported and deposited on the second molten cadmium cathode.