| Patent Number |
Title Of Patent |
Date Issued |
| 7410561 |
Three-electrode metal oxide reduction cell |
August 12, 2008 |
| 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 i |
| 6911134 |
Three-electrode metal oxide reduction cell |
June 28, 2005 |
| 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 i |
| 5336450 |
Process to remove rare earth from IFR electrolyte |
August 9, 1994 |
| The invention is a process for the removal of rare earths from molten chloride electrolyte salts used in the reprocessing of integrated fast reactor fuel (IFR). The process can be used either continuously during normal operation of the electrorefiner or as a batch process. The process |
| 5160367 |
Salt transport extraction of transuranium elements from lwr fuel |
November 3, 1992 |
| 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 |
| 5147616 |
Magnesium transport extraction of transuranium elements from LWR fuel |
September 15, 1992 |
| 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 8 |
| 5141723 |
Uranium chloride extraction of transuranium elements from LWR fuel |
August 25, 1992 |
| 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 |
| 5096545 |
Plutonium recovery from spent reactor fuel by uranium displacement |
March 17, 1992 |
| 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 |
| 4880506 |
Electrorefining process and apparatus for recovery of uranium and a mixture of uranium and pluto |
November 14, 1989 |
| 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 |
| 4814046 |
Process to separate transuranic elements from nuclear waste |
March 21, 1989 |
| A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for |
| 4499663 |
Method of fabricating a monolithic core for a solid oxide fuel cell |
February 19, 1985 |
| A method is disclosed for forming a core for use in a solid oxide fuel cell that electrochemically combines fuel and oxidant for generating galvanic output. The core has an array of electrolyte and interconnect walls that are substantially devoid of any composite inert materials for supp |
| 4476198 |
Solid oxide fuel cell having monolithic core |
October 9, 1984 |
| A solid oxide fuel cell for electrochemically combining fuel and oxidant for generating galvanic output, wherein the cell core has an array of electrolyte and interconnect walls that are substantially devoid of any composite inert materials for support. Instead, the core is monolithic, |
| 4115632 |
Method of preparing electrolyte for use in fuel cells |
September 19, 1978 |
| 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 mixi |
