Patents by Inventor Edward J. Lahoda

Edward J. Lahoda 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: 20230352199
    Abstract: The invention relates to SiC ceramic matrix composite (CMC) claddings with metallic, ceramic and/or multilayer coatings applied on the outer surface for improved corrosion resistance and hermeticity protection. The coating includes one or more materials selected from FeCrAl, Y, Zr and Al—Cr alloys, Cr2O3, ZrO2 and other oxides, chromium carbides, CrN, Zr- and Y-silicates and silicides. The coatings are applied employing a variety of known surface treatment technologies including cold spray, thermal spray process, physical vapor deposition process (PVD), and slurry coating.
    Type: Application
    Filed: April 24, 2023
    Publication date: November 2, 2023
    Applicant: Westinghouse Electric Company LLC
    Inventors: Edward J. LAHODA, Peng XU, Roberto L. OELRICH, JR., Hwasung YEOM, Kumar SRIDHARAN
  • Publication number: 20230343475
    Abstract: Channel boxes for a boiling water reactor and methods of manufacture thereof are provided. The channel box comprises a substrate and a first layer. The substrate comprises a tubular shape. The substrate comprises silicon carbide fibers. The first layer is deposited on a first surface of the substrate and the first layer comprises a corrosion resistant metallic composition.
    Type: Application
    Filed: May 3, 2021
    Publication date: October 26, 2023
    Applicant: Westinghouse Electric Company LLC
    Inventors: Michael SIVACK, Peng XU, Edward J. LAHODA
  • Publication number: 20230223159
    Abstract: Nuclear fuel cladding for fast reactors, assemblies thereof, and methods of manufacture thereof are provided. The nuclear fuel cladding comprises a substrate, a first layer, and a second layer. The substrate a tubular shape. The first layer is deposited over an external surface of the substrate. The first layer comprises a corrosion resistant composition. The second layer is disposed over the first layer. The second layer comprises silicon carbide fibers infiltrated with silicon carbide. The second layer is configured to inhibit outward creep of the substrate.
    Type: Application
    Filed: April 22, 2021
    Publication date: July 13, 2023
    Applicant: Westinghouse Electric Company LLC
    Inventors: Edward J. LAHODA, Paolo FERRONI, Fausto FRANCESCHINI
  • Publication number: 20230132157
    Abstract: Annular nuclear fuel rods are disclosed. The annular nuclear fuel rods include an outer cladding tube made of ceramic composite or cermet composite, an inner cladding tube made of ceramic composite or cermet composite, a nuclear fuel region located between the outer cladding tube and inner cladding tube, and an open channel for liquid coolant to flow.
    Type: Application
    Filed: October 21, 2021
    Publication date: April 27, 2023
    Applicant: Westinghouse Electric Company LLC
    Inventors: Luke C. OLSON, Kathryn E. METZGER, Edward J. LAHODA, Elwyn ROBERTS, Michael R. ICKES, Paolo FERRONI, Denise Adorno LOPES, Luke D. CZERNIAK, Fausto FRANCESCHINI
  • Publication number: 20230095751
    Abstract: A method for making an improved nuclear fuel cladding tube includes reinforcing a Zr alloy tube by first winding or braiding ceramic yarn directly around the tube to form a ceramic covering, then physically bonding the ceramic covering to the tube by applying a first coating selected from the group consisting of Nb, Nb alloy, Nb oxide, Cr, Cr oxide, Cr alloy, or combinations thereof, by one of a thermal deposition process or a physical deposition process to provide structural support member for the Zr tube, and optionally applying a second coating and optionally applying a third coating by one of a thermal deposition process or a physical deposition process. If the tube softens at 800° C.-1000° C., the structural support tube will reinforce the Zr alloy tube against ballooning and bursting, thereby preventing the release of fission products to the reactor coolant.
    Type: Application
    Filed: June 29, 2022
    Publication date: March 30, 2023
    Applicant: Westinghouse Electric Company LLC
    Inventor: Edward J. LAHODA
  • Publication number: 20230036331
    Abstract: A nuclear fuel assembly and a method of manufacture thereof are provided. The method comprises depositing a thermally conductive layer onto at least a portion of at least two nuclear fuel layers to create at least two at least partially coated layers. The method comprises stacking the at least two coated layers and bonding the at least two coated layers to form a nuclear fuel assembly.
    Type: Application
    Filed: January 8, 2021
    Publication date: February 2, 2023
    Applicant: Westinghouse Electric Company LLC
    Inventors: Edward J. LAHODA, Clinton B. ARMSTRONG, Lyman J. PETROSKY
  • Patent number: 11551822
    Abstract: A method of forming a water resistant boundary on a fissile material for use in a water cooled nuclear reactor is described. The method comprises mixing a powdered fissile material selected from the group consisting of UN and U3Si2 with an additive selected from oxidation resistant materials having a melting or softening point lower than the sintering temperature of the fissile material, pressing the mixed fissile and additive materials into a pellet, sintering the pellet to a temperature greater than the melting point of the additive. Alternatively, if the melting point of the oxidation resistant particles is greater than the sintering temperature of UN or U3Si2, then the oxidation resistant particles can have a particle size distribution less than that of the UN or U3Si2.
    Type: Grant
    Filed: September 13, 2021
    Date of Patent: January 10, 2023
    Assignee: Westinghouse Electric Company LLC
    Inventors: Edward J. Lahoda, Peng Xu, Robert L. Oelrich, Jr., Hemant Shah, Jonathan Wright, Lu Cai
  • Publication number: 20220384062
    Abstract: The present disclosure is generally related to methods, systems and devices for forming a randomized grain structure coating on a substrate of a component for use in a nuclear reactor to provide protection against corrosion and, more particularly, is directed to improved methods, systems and devices for forming a randomized grain structure coating on a zirconium alloy nuclear fuel cladding tube using a cathodic arc (CA) physical vapor deposition (PVD) process to provide protection against corrosion in both normal operation and in transient and accidents of the nuclear reactor.
    Type: Application
    Filed: May 27, 2021
    Publication date: December 1, 2022
    Applicant: Westinghouse Electric Company LLC
    Inventors: Edward J. LAHODA, Benjamin R. MAIER, Allan W. JAWORSKI, Jonathan WRIGHT, Jorie L. WALTERS, Robert A. TERRY
  • Publication number: 20220375631
    Abstract: A nuclear fuel cladding tube is described herein that includes a zirconium alloy tube having an outer wear and oxidation resistant ceramic coating selected from the group consisting of CrN, Cr2N, CrWN, CrZrN, and combinations thereof. The cladding may have an intermediate layer formed between the tube and the outer ceramic coating. The intermediate layer may be selected from the group consisting of Ta, W, Mo, Nb, and combinations thereof. Both the intermediate layer and the outer ceramic coating may be deposited by physical vapor deposition.
    Type: Application
    Filed: September 12, 2020
    Publication date: November 24, 2022
    Applicant: Westinghouse Electric Company LLC
    Inventors: Magnus NORLEN, Jonathan WRIGHT, Edward J. LAHODA, Magnus LIMBACK, Jorie L. WALTERS, Javier E. ROMEO, Benjamin R. MAIER
  • Patent number: 11488730
    Abstract: Disclosed herein is a method comprising coating a fissile, uranium-containing ceramic material with a water-resistant layer, the layer being non-reactive with the fissile, uranium-containing ceramic material. The coating is applied to a surface of the fissile, uranium-containing ceramic material. Also disclosed is a fuel for use in a nuclear reactor.
    Type: Grant
    Filed: October 7, 2020
    Date of Patent: November 1, 2022
    Assignee: Westinghouse Electric Company LLC
    Inventors: Edward J. Lahoda, Peng Xu, Lu Cai
  • Publication number: 20220333254
    Abstract: A method is described herein that produces UN from UF6 in at most two steps comprising UF6?intermediate?UN. The principle of the reaction is that in a first step, UF6 would be reduced to UxNy, where x may be an integer selected from 1 and 3, and y is an integer selected from 1 and 2. Reduction occurs at or near the surface of a gaseous membrane electrode where it is also in contact with a nitrogen bearing salt. In a second step, UxNy decomposes to UN and N2 gas, either in the same reactor as the first step or after removal to a separate unit for further processing.
    Type: Application
    Filed: September 4, 2020
    Publication date: October 20, 2022
    Applicant: Westinghouse Electric Company LLC
    Inventors: Luke C. OLSON, Kathryn E. METZGER, Edward J. Lahoda
  • Patent number: 11443857
    Abstract: A zirconium alloy cladding tube for use in a water cooled nuclear reactor under normal operating conditions and under high temperature oxidation conditions is described. The cladding tube has a coating uniformly deposited thereon. The coating, which may be up to 300 microns thick, is selected from the group consisting of chromium, a chromium-based alloy, and combinations thereof.
    Type: Grant
    Filed: September 17, 2019
    Date of Patent: September 13, 2022
    Assignee: Westinghouse Electric Company LLC
    Inventors: Edward J. Lahoda, Peng Xu, Zeses Karoutas, Sumit Ray, Kumar Sridharan, Benjamin Maier, Greg Johnson
  • Patent number: 11404175
    Abstract: A method for making an improved nuclear fuel cladding tube includes reinforcing a Zr alloy tube by first winding or braiding ceramic yarn directly around the tube to form a ceramic covering, then physically bonding the ceramic covering to the tube by applying a first coating selected from the group consisting of Nb, Nb alloy, Nb oxide, Cr, Cr oxide, Cr alloy, or combinations thereof, by one of a thermal deposition process or a physical deposition process to provide structural support member for the Zr tube, and optionally applying a second coating and optionally applying a third coating by one of a thermal deposition process or a physical deposition process. If the tube softens at 800° C.-1000° C., the structural support tube will reinforce the Zr alloy tube against ballooning and bursting, thereby preventing the release of fission products to the reactor coolant.
    Type: Grant
    Filed: July 3, 2019
    Date of Patent: August 2, 2022
    Assignee: Westinghouse Electric Company LLC
    Inventor: Edward J. Lahoda
  • Publication number: 20220108808
    Abstract: A control rod for a nuclear fuel assembly is described herein that includes a neutron absorbing material having a melting point greater than 1500° C. that does not form a eutectic with a melting point less than 1500° C., and may further include a cladding material having a melting point greater than 1500° C. The cladding material is selected from the group consisting of silicon carbide, zirconium, a zirconium alloy, tungsten, and molybdenum. The absorbing material is selected from the group consisting of Gd2O3, Ir, B4C, Re, and Hf. The metal cladding or the absorbing material may be coated with an anti-oxidation coating of Cr with or without a Nb intermediate layer.
    Type: Application
    Filed: November 9, 2021
    Publication date: April 7, 2022
    Applicant: Westinghouse Electric Company LLC
    Inventors: Edward J. LAHODA, Frank A. BOYLAN, Ho Q. LAM, Mitchell E. NISSLEY, Raymond E. SCHNEIDER, Robert L. OELRICH, Sumit RAY, Radu POMIRLEANU, Zeses KAROUTAS, Michael J. HONE
  • Patent number: 11289213
    Abstract: A control rod for a nuclear fuel assembly is described herein that includes a neutron absorbing material having a melting point greater than 1500° C. that does not form a eutectic with a melting point less than 1500° C., and may further include a cladding material having a melting point greater than 1500° C. The cladding material is selected from the group consisting of silicon carbide, zirconium, a zirconium alloy, tungsten, and molybdenum. The absorbing material is selected from the group consisting of Gd2O3, Ir, B4C, Re, and Hf. The metal cladding or the absorbing material may be coated with an anti-oxidation coating of Cr with or without a Nb intermediate layer.
    Type: Grant
    Filed: August 1, 2018
    Date of Patent: March 29, 2022
    Assignee: Westinghouse Electric Company LLC
    Inventors: Edward J. Lahoda, Frank A. Boylan, Ho Q. Lam, Mitchell E. Nissley, Raymond E. Schneider, Robert L. Oelrich, Sumit Ray, Radu Pomirleanu, Zeses Karoutas, Michael J. Hone
  • Publication number: 20220084694
    Abstract: An improvement in a nuclear fuel rod is disclosed. The improved fuel rod includes a cladding tube, a plurality of fuel pellets stacked within the cladding tube, and a liquid material filling the gap between the fuel pellets and the cladding tube. The liquid material is selected from those having a thermal conductivity higher than that of helium, a melting point lower than about 400° C., a boiling point higher than 1600° C., and which are capable of wetting both the fuel pellets and the cladding sufficient to form a protective layer over the pellets and to wick into openings that may form in the cladding.
    Type: Application
    Filed: March 5, 2020
    Publication date: March 17, 2022
    Applicant: Westinghouse Electric Company LLC
    Inventors: Edward J. LAHODA, Peng XU, Lu CAI, Yun LONG, John LYONS
  • Publication number: 20220068511
    Abstract: A method of forming a water resistant boundary on a fissile material for use in a water cooled nuclear reactor is described. The method comprises mixing a powdered fissile material selected from the group consisting of UN and U3Si2 with an additive selected from oxidation resistant materials having a melting or softening point lower than the sintering temperature of the fissile material, pressing the mixed fissile and additive materials into a pellet, sintering the pellet to a temperature greater than the melting point of the additive.
    Type: Application
    Filed: September 13, 2021
    Publication date: March 3, 2022
    Applicant: Westinghouse Electric Company LLC
    Inventors: Edward J. LAHODA, Peng XU, Robert L. OELRICH, JR., Hemant SHAH, Jonathan WRIGHT, Lu CAI
  • Publication number: 20210354993
    Abstract: Methods and systems for separation of thorium from uranium and their decay products are provided. The method comprises combining a nuclear fuel feedstock comprising thorium and uranium with a first acid to form a first solution. The first solution is contacted an ion exchange resin that is selective for thorium or uranium. The thorium or uranium is at least partially removed from the first solution by binding the thorium or uranium to the ion exchange resin thereby forming a second solution. The second solution is combined with oxalic acid to precipitate uranium or thorium from the second solution to form a precipitate. The precipitate is separated from the second solution.
    Type: Application
    Filed: May 18, 2020
    Publication date: November 18, 2021
    Applicant: Westinghouse Electric Company LLC
    Inventors: John L. LYONS, Edward J. LAHODA, Michael R. ICKES, Daniel C. FLAHIVE, Frank C. GIFT, JR., William F. LENZKE
  • Patent number: 11145425
    Abstract: A method of forming a water resistant boundary on a fissile material for use in a water cooled nuclear reactor is described. The method comprises mixing a powdered fissile material selected from the group consisting of UN and U3Si2 with an additive selected from oxidation resistant materials having a melting or softening point lower than the sintering temperature of the fissile material, pressing the mixed fissile and additive materials into a pellet, sintering the pellet to a temperature greater than the melting point of the additive. Alternatively, if the melting point of the oxidation resistant particles is greater than the sintering temperature of UN or U3Si2, then the oxidation resistant particles can have a particle size distribution less than that of the UN or U3Si2.
    Type: Grant
    Filed: January 29, 2019
    Date of Patent: October 12, 2021
    Assignee: Westinghouse Electric Company LLC
    Inventors: Edward J. Lahoda, Peng Xu, Robert L. Oelrich, Jr., Hemant Shah, Jonathan Wright, Lu Cai
  • Patent number: 11062810
    Abstract: The invention relates generally to uranium fuel in a nuclear reactor and, more particularly, the inclusion of a fuel additive component to the bulk fuel material. The fuel additive component is selected and provided in an amount such that it is effective to improve one or more properties of the bulk fuel material. The fuel additive component has a grain size that is less than the grain size of the bulk fuel material. The granular fuel additive component coats or covers the granular bulk fuel material.
    Type: Grant
    Filed: April 8, 2019
    Date of Patent: July 13, 2021
    Assignee: Westinghouse Electric Company LLC
    Inventor: Edward J. Lahoda