Patents by Inventor James L. Willit

James L. Willit has filed for patents to protect the following inventions. This listing includes patent applications that are pending as well as patents that have already been granted by the United States Patent and Trademark Office (USPTO).

  • Publication number: 20120160666
    Abstract: An electrolytic oxide reduction system according to a non-limiting embodiment of the present invention may include a plurality of anode assemblies, a plurality of cathode assemblies, and a lift system configured to engage the anode and cathode assemblies. The cathode assemblies may be alternately arranged with the anode assemblies such that each cathode assembly is flanked by two anode assemblies. The lift system may be configured to selectively engage the anode and cathode assemblies so as to allow the simultaneous lifting of any combination of the anode and cathode assemblies (whether adjacent or non-adjacent).
    Type: Application
    Filed: December 23, 2010
    Publication date: June 28, 2012
    Applicant: GE-HITACHI NUCLEAR ENERGY AMERICAS LLC
    Inventors: Stanley G. Wiedmeyer, Laurel A. Barnes, Mark A. Williamson, James L. Willit, John F. Berger
  • Publication number: 20120160703
    Abstract: Power distribution systems are useable in electrolytic reduction systems and include several cathode and anode assembly electrical contacts that permit flexible modular assembly numbers and placement in standardized connection configurations. Electrical contacts may be arranged at any position where assembly contact is desired. Electrical power may be provided via power cables attached to seating assemblies of the electrical contacts. Cathode and anode assembly electrical contacts may provide electrical power at any desired levels. Pairs of anode and cathode assembly electrical contacts may provide equal and opposite electrical power; different cathode assembly electrical contacts may provide different levels of electrical power to a same or different modular cathode assembly.
    Type: Application
    Filed: December 23, 2010
    Publication date: June 28, 2012
    Applicant: GE-HITACHI NUCLEAR ENERGY AMERICAS LLC
    Inventors: Eugene R. Koehl, Laurel A. Barnes, Stanley G. Wiedmeyer, Mark A. Williamson, James L. Willit
  • Publication number: 20120160704
    Abstract: Modular anode assemblies are used in electrolytic oxide reduction systems for scalable reduced metal production via electrolysis. Assemblies include a channel frame connected to several anode rods extending into an electrolyte. An electrical system powers the rods while being insulated from the channel frame. A cooling system removes heat from anode rods and the electrical system. An anode guard attaches to the channel frame to prevent accidental electrocution or damage during handling or repositioning. Each anode rod may be divided into upper and lower sections to permit easy repair and swapping out of lower sections. The modular assemblies may have standardized components to permit placement at multiple points within a reducing system. Example methods may operate an electrolytic oxide reduction system by positioning the modular anode assemblies in the reduction system and applying electrical power to the plurality of anode assemblies.
    Type: Application
    Filed: December 23, 2010
    Publication date: June 28, 2012
    Applicant: GE-HITACHI NUCLEAR ENERGY AMERICAS LLC
    Inventors: Stanley G. Wiedmeyer, Laurel A. Barnes, Mark A. Williamson, James L. Willit
  • Publication number: 20120160668
    Abstract: An electrolytic oxide reduction system according to a non-limiting embodiment of the present invention may include a plurality of anode assemblies and an anode shroud for each of the anode assemblies. The anode shroud may be used to dilute, cool, and/or remove off-gas from the electrolytic oxide reduction system. The anode shroud may include a body portion having a tapered upper section that includes an apex. The body portion may have an inner wall that defines an off-gas collection cavity. A chimney structure may extend from the apex of the upper section and be connected to the off-gas collection cavity of the body portion. The chimney structure may include an inner tube within an outer tube. Accordingly, a sweep gas/cooling gas may be supplied down the annular space between the inner and outer tubes, while the off-gas may be removed through an exit path defined by the inner tube.
    Type: Application
    Filed: December 23, 2010
    Publication date: June 28, 2012
    Applicant: GE-HITACHI NUCLEAR ENERGY AMERICAS LLC
    Inventors: James L. Bailey, Laurel A. Barnes, Stanley G. Wiedmeyer, Mark A. Williamson, James L. Willit
  • Patent number: 8097142
    Abstract: The present invention provides a method of simultaneously removing uranium and transuranics from metallic nuclear fuel in an electrorefiner. In the method, a potential difference is established between an anode basket containing the fuel and a solid cathode of the electrorefiner, thereby creating a diffusion layer of uranium and transuranic ions at the solid cathode, a first current density at the anode basket, and a second current density at the solid cathode. The ratio of anode basket area to solid cathode area is selected based on the total concentration of uranium and transuranic metals in a molten halide electrolyte in the electrorefiner and the effective thickness of the diffusion layer at the solid cathode, such that the established first and second current densities result in both codeposition of uranium and transuranic metals on the solid cathode and oxidation of the metallic nuclear fuel in the anode basket.
    Type: Grant
    Filed: March 2, 2009
    Date of Patent: January 17, 2012
    Assignee: Uchicago Argonne, LLC.
    Inventors: James L. Willit, Mark A. Williamson
  • Publication number: 20110180409
    Abstract: The present invention provides a method of simultaneously removing uranium and transuranics from metallic nuclear fuel in an electrorefiner. In the method, a potential difference is established between the anode basket and solid cathode of the electrorefiner, thereby creating a diffusion layer of uranium and transuranic ions at the solid cathode, a first current density at the anode basket, and a second current density at the solid cathode. The ratio of anode basket area to solid cathode area that is selected based on the total concentration of uranium and transuranic metals in a molten halide electrolyte in the refiner and the effective thickness of the diffusion layer at the solid cathode, such that the established first and second current densities result in both codeposition of uranium and transuranic metals on the solid cathode and oxidation of the metallic nuclear fuel in the anode basket.
    Type: Application
    Filed: March 2, 2009
    Publication date: July 28, 2011
    Inventors: James L. Willit, Mark A. Williamson
  • Patent number: 7799185
    Abstract: An improved process and device for the recovery of the minor actinides and the transuranic elements (TRU's) from a molten salt electrolyte. The process involves placing the device, an electrically non-conducting barrier between an anode salt and a cathode salt. The porous barrier allows uranium to diffuse between the anode and cathode, yet slows the diffusion of uranium ions so as to cause depletion of uranium ions in the catholyte. This allows for the eventual preferential deposition of transuranics present in spent nuclear fuel such as Np, Pu, Am, Cm. The device also comprises an uranium oxidation anode. The oxidation anode is solid uranium metal in the form of spent nuclear fuel. The spent fuel is placed in a ferric metal anode basket which serves as the electrical lead or contact between the molten electrolyte and the anodic uranium metal.
    Type: Grant
    Filed: September 11, 2006
    Date of Patent: September 21, 2010
    Assignee: The United States of America as represented by the United States Department of Energy
    Inventor: James L. Willit
  • Patent number: 7722757
    Abstract: A method and device for the production of hydrogen from water and electricity using an active metal alloy. The active metal alloy reacts with water producing hydrogen and a metal hydroxide. The metal hydroxide is consumed, restoring the active metal alloy, by applying a voltage between the active metal alloy and the metal hydroxide. As the process is sustainable, only water and electricity is required to sustain the reaction generating hydrogen.
    Type: Grant
    Filed: September 29, 2006
    Date of Patent: May 25, 2010
    Assignee: The United States of America as represented by the United States Department of Energy
    Inventors: William E. Miller, Victor A. Maroni, James L. Willit
  • Patent number: 7638026
    Abstract: This is a single stage process for treating spent nuclear fuel from light water reactors. The spent nuclear fuel, uranium oxide, UO2, is added to a solution of UCl4 dissolved 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.
    Type: Grant
    Filed: August 24, 2005
    Date of Patent: December 29, 2009
    Assignee: The United States of America as represented by the United States Department of Energy
    Inventors: James L. Willit, John P. Ackerman, Mark A. Williamson
  • Patent number: 7267754
    Abstract: An improved process and device for the recovery of the minor actinides and the transuranic elements (TRU's) from a molten salt electrolyte. The process involves placing the device, an electrically non-conducting barrier between an anode salt and a cathode salt. The porous barrier allows uranium to diffuse between the anode and cathode, yet slows the diffusion of uranium ions so as to cause depletion of uranium ions in the catholyte. This allows for the eventual preferential deposition of transuranics present in spent nuclear fuel such as Np, Pu, Am, Cm. The device also comprises an uranium oxidation anode. The oxidation anode is solid uranium metal in the form of spent nuclear fuel. The spent fuel is placed in a ferric metal anode basket which serves as the electrical lead or contact between the molten electrolyte and the anodic uranium metal.
    Type: Grant
    Filed: January 21, 2004
    Date of Patent: September 11, 2007
    Assignee: U.S. Department of Energy
    Inventor: James L. Willit
  • Publication number: 20040134785
    Abstract: A nuclear fuel electrorefiner for recovering uranium from nuclear material containing uranium. A cylindrical vessel with having a longitudinal axis has a product collector movable axially of the vessel. Circular cathodes extend axially of and radially spaced inwardly of the vessel with a plurality of generally polyhedron-shaped anode baskets having at least one face aligned with a radius of said vessel and circumferentially spaced from adjacent anode baskets and concentric with respect to the cathodes in the vessel. A plurality of axially extending metal rods are insulated from and placed between the anode baskets. Mechanism outside of the vessel rotate the anode baskets and the metal rods with respect to the cathodes, and an electrical power supply in selective electrical communication with said cathode and said anode baskets and said metal rods to cause uranium values to move between the and when current flow is in a first direction uranium values in said anode baskets and the metal rods to the cathodes.
    Type: Application
    Filed: January 9, 2003
    Publication date: July 15, 2004
    Applicant: The University of Chicago
    Inventors: Eddie C. Gay, James L. Willit, Donald E. Preuss
  • Patent number: 5711019
    Abstract: A method of removing Li.sub.2 O present in an electrolyte predominantly of LiCl and KCl. The electrolyte is heated to a temperature not less than about 500.degree. C. and then Al is introduced into the electrolyte in an amount in excess of the stoichiometric amount needed to convert the Li.sub.2 O to a Li-Al alloy and lithium aluminate salt. The salt and aluminum are maintained in contact with agitation for a time sufficient to convert the Li.sub.2 O.
    Type: Grant
    Filed: January 31, 1996
    Date of Patent: January 20, 1998
    Assignee: The United States of America as represented by the United States Department of Energy
    Inventors: Zygmunt Tomczuk, William E. Miller, Gerald K. Johnson, James L. Willit