Patents by Inventor Lu CAI

Lu CAI 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: 20230209932
    Abstract: Provided are a display panel and a manufacturing method thereof, and a display device. The display panel includes a base substrate and a plurality of sub-pixels. At least one sub-pixel includes a light-emitting element; a first transistor; a capacitor including a first electrode and a second electrode plate; a second transistor including a second active layer including a third and a fourth electrode area, and a second channel area; and a third transistor including a third active layer, and a third gate electrode connected to a reset line, the third active layer including a fifth electrode area, a sixth electrode area directly connected to an initialization line via a via hole, and a third channel area. An orthographic projection of the initialization line on the base substrate is located between orthographic projections of the reset line and the gate line on the base substrate.
    Type: Application
    Filed: October 22, 2021
    Publication date: June 29, 2023
    Applicants: ORDOS YUANSHENG OPTOELECTRONICS CO., LTD., BOE TECHNOLOGY GROUP CO., LTD.
    Inventors: Xu WANG, Zihua LI, Lu CAI, Qiang GUO, Wenqiang JIN, Chunbo LI, Qiang WANG, Xudong WANG, Ruiqing ZHANG
  • 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
  • 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
  • Patent number: 11444263
    Abstract: A flexible display panel. The flexible display panel includes: a flexible substrate; a display element arranged on the flexible substrate; and a packaging layer covering the display element, the packaging layer including an inorganic thin film and an organic thin film that are stacked alternately, in which two protrusion structures that are engaged with each other are arranged between at least two adjacent thin films of the packaging layer.
    Type: Grant
    Filed: October 12, 2019
    Date of Patent: September 13, 2022
    Assignees: Ordos Yuansheng Optoelectronics Co., Ltd., Beijing BOE Technology Development Co., Ltd.
    Inventors: Xiaodong Meng, Lingling Ma, Zihua Li, Zhibo Wen, Hengbo Liu, Yu Yuan, Lu Cai, Dong Xu, Guofang Xu, Xinpeng Gao, Qiang Wang, Ruiqing Zhang, Qiang Guo, Wenqiang Jin, Xudong Wang
  • 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
  • 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
  • Publication number: 20210020321
    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: Application
    Filed: October 7, 2020
    Publication date: January 21, 2021
    Applicant: Westinghouse Electric Company LLC
    Inventors: Edward J. LAHODA, Peng XU, Lu CAI
  • Publication number: 20200365826
    Abstract: The present disclosure provides a flexible display panel, a method for packaging the same, and a display device. The flexible display panel includes: a flexible substrate; a display element arranged on the flexible substrate; and a packaging layer covering the display element, the packaging layer including an inorganic thin film and an organic thin film that are stacked alternately, in which two protrusion structures that are engaged with each other are arranged between at least two adjacent thin films of the packaging layer.
    Type: Application
    Filed: October 12, 2019
    Publication date: November 19, 2020
    Applicants: ORDOS YUANSHENG OPTOELECTRONICS CO., LTD., BOE TECHNOLOGY GROUP CO., LTD.
    Inventors: Xiaodong MENG, Lingling MA, Zihua LI, Zhibo WEN, Hengbo LIU, Yu YUAN, Lu CAI, Dong XU, Guofang XU, Xinpeng GAO, Qiang WANG, Ruiqing ZHANG, Qiang GUO, Wenqiang JIN, Xudong WANG
  • Patent number: 10803999
    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 coating the fissile material, such as a pellet of U3Si2 and/or the grain boundaries, to a desired thickness with a suitable coating material, such as atomic layer deposition or a thermal spray process. The coating material may be any non-reactive material with a solubility at least as low as that of UO2. Exemplary coating materials include ZrSiO4, FeCrAl, Cr, Zr, Al—Cr, CrAl, ZrO2, CeO2, TiO2, SiO2, UO2, ZrB2, Na2O—B2O3—SiO2—Al2O3 glass, Al2O3, Cr2O3, carbon, and SiC, and combinations thereof. The water resistant layer may be overlayed with a burnable absorber layer, such as ZrB2 or B2O3—SiO2 glass.
    Type: Grant
    Filed: February 16, 2018
    Date of Patent: October 13, 2020
    Assignee: Westinghouse Electric Company LLC
    Inventors: Edward J. Lahoda, Peng Xu, Lu Cai
  • Publication number: 20200258642
    Abstract: The present invention relates to nuclear fuel compositions including uranium dioxide with integral fuel burnable absorber, and triuranium disilicide and a composite of uranium mononitride and triuranium disilicide with or without integral fuel burnable absorber, and methods of sintering these compositions. The sintering is conducted using SPS/FAST apparatus and techniques. The sintering time and temperature is reduced using SPS/FAST as compared to conventional sintering methods for nuclear fuel compositions. The nuclear fuel compositions of the present invention are particularly useful in light water reactors.
    Type: Application
    Filed: February 12, 2019
    Publication date: August 13, 2020
    Applicant: WESTINGHOUSE ELECTRIC COMPANY, LLC
    Inventors: PENG XU, LU CAI, SYLVESTER F. OGUNJI, EDWARD J. LAHODA, LARS HALLSTADIUS
  • Publication number: 20200111584
    Abstract: An improved nuclear fuel that has enhanced oxidation resistance and a process for making it are disclosed. The fuel comprises a composite of U235 enriched U3Si2 particles and an amount less than 30% by weight of UO2 particles positioned along the surface of the U3Si2 particles. The composite may be compressed into a pellet form. The process comprises forming a layer of UO2 on the surface of U3Si2 particles, either by exposing U3Si2 particles to an atmosphere of up to 15% oxygen by volume dispersed in an inert gas for a period of time and at a temperature sufficient to form UO2 at the U3Si2 particle surface, or by mixing U3Si2 particles with an amount up to 30% by weight of UO2 particles.
    Type: Application
    Filed: November 27, 2019
    Publication date: April 9, 2020
    Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
    Inventors: EDWARD J. LAHODA, HEMANT SHAH, PENG XU, LU CAI
  • Publication number: 20190237206
    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: Application
    Filed: January 29, 2019
    Publication date: August 1, 2019
    Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
    Inventors: EDWARD J. LAHODA, PENG XU, ROBERT L. OELRICH, JR., HEMANT SHAH, JONATHAN WRIGHT, LU CAI
  • Patent number: 10350856
    Abstract: The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The composition includes a master alloy including one or more alloying elements selected from chromium, silicon and aluminum, a chemical activator and an inert filler. The alloying element(s) is deposited or are co-deposited on the cladding using a pack cementation process. When the coated zirconium alloy cladding is exposed to and contacted with water in a nuclear reactor, a protective oxide layer can form on the coated surface of the cladding.
    Type: Grant
    Filed: November 2, 2017
    Date of Patent: July 16, 2019
    Assignee: Westinghouse Electric Company LLC
    Inventors: Peng Xu, Lu Cai
  • Publication number: 20190074095
    Abstract: An improved nuclear fuel that has enhanced oxidation resistance and a process for making it are disclosed. The fuel comprises a composite of U235 enriched U3Si2 particles and an amount less than 30% by weight of UO2 particles positioned along the surface of the U3Si2 particles. The composite may be compressed into a pellet form. The process comprises forming a layer of UO2 on the surface of U3Si2 particles, either by exposing U3Si2 particles to an atmosphere of up to 15% oxygen by volume dispersed in an inert gas for a period of time and at a temperature sufficient to form UO2 at the U3Si2 particle surface, or by mixing U3Si2 particles with an amount up to 30% by weight of UO2 particles.
    Type: Application
    Filed: September 5, 2017
    Publication date: March 7, 2019
    Applicant: WESTINGHOUSE ELECTRIC COMPANY, LLC
    Inventors: EDWARD J. LAHODA, HEMANT SHAH, PENG XU, LU CAI
  • Publication number: 20180268946
    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 coating the fissile material, such as a pellet of U3Si2 and/or the grain boundaries, to a desired thickness with a suitable coating material, such as atomic layer deposition or a thermal spray process. The coating material may be any non-reactive material with a solubility at least as low as that of UO2. Exemplary coating materials include ZrSiO4, FeCrAl, Cr, Zr, Al—Cr, CrAl, ZrO2, CeO2, TiO2, SiO2, UO2, ZrB2, Na2O—B2O3—SiO2—Al2O3 glass, Al2O3, Cr2O3, carbon, and SiC, and combinations thereof. The water resistant layer may be overlayed with a burnable absorber layer, such as ZrB2 or B2O3—SiO2 glass.
    Type: Application
    Filed: February 16, 2018
    Publication date: September 20, 2018
    Applicant: WESTINGHOUSE ELECTRIC COMPANY, LLC
    Inventors: EDWARD J. LAHODA, PENG XU, LU CAI
  • Publication number: 20180056628
    Abstract: The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The composition includes a master alloy including one or more alloying elements selected from chromium, silicon and aluminum, a chemical activator and an inert filler. The alloying element(s) is deposited or are co-deposited on the cladding using a pack cementation process. When the coated zirconium alloy cladding is exposed to and contacted with water in a nuclear reactor, a protective oxide layer can form on the coated surface of the cladding.
    Type: Application
    Filed: November 2, 2017
    Publication date: March 1, 2018
    Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
    Inventors: PENG XU, LU CAI
  • Patent number: 9844923
    Abstract: The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The composition includes a master alloy including one or more alloying elements selected from chromium, silicon and aluminum, a chemical activator and an inert filler. The alloying element(s) is deposited or are co-deposited on the cladding using a pack cementation process. When the coated zirconium alloy cladding is exposed to and contacted with water in a nuclear reactor, a protective oxide layer can form on the coated surface of the cladding.
    Type: Grant
    Filed: August 14, 2015
    Date of Patent: December 19, 2017
    Assignee: Westinghouse Electric Company LLC
    Inventors: Peng Xu, Lu Cai
  • Publication number: 20170043555
    Abstract: The invention relates to compositions and methods for coating a zirconium alloy cladding of a fuel element for a nuclear water reactor. The composition includes a master alloy including one or more alloying elements selected from chromium, silicon and aluminum, a chemical activator and an inert filler. The alloying element(s) is deposited or are co-deposited on the cladding using a pack cementation process. When the coated zirconium alloy cladding is exposed to and contacted with water in a nuclear reactor, a protective oxide layer can form on the coated surface of the cladding.
    Type: Application
    Filed: August 14, 2015
    Publication date: February 16, 2017
    Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
    Inventors: Peng XU, Lu CAI