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).
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Publication number: 20240240041Abstract: This disclosure relates to a radiation-curable composition comprising (A) at least one water-soluble monofunctional ethylenically unsaturated monomer; (B) at least one water-soluble non-curable component, wherein the weighted average melting point of component (B) is more than 22° C. preferably more than 25° C.; and (C) at least one photoinitiator.Type: ApplicationFiled: April 29, 2022Publication date: July 18, 2024Inventors: Fan ZHANG, Jie LU, Chong Xi WANG, Zhi Zhong CAI
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Publication number: 20240163521Abstract: The present application provides techniques for displaying information pages. The techniques comprise in response to an operation of starting a client application by a user, displaying a first page comprising a navigation bar and displaying an image of a recommended creator in a preset area of the navigation bar; and in response to detecting a touch operation on the image of the recommended creator, jumping from the first page to a second page and displaying the image of the recommended creator at a top position in a predetermined area of the second page, wherein the predetermined area is configured to display images of a plurality of recommended creators based on information of the user.Type: ApplicationFiled: November 9, 2023Publication date: May 16, 2024Inventors: Binwu JIN, Lu CAI, Xin JING, Tongbin LV
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Publication number: 20230209932Abstract: 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: ApplicationFiled: October 22, 2021Publication date: June 29, 2023Applicants: 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
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Patent number: 11551822Abstract: 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: GrantFiled: September 13, 2021Date of Patent: January 10, 2023Assignee: Westinghouse Electric Company LLCInventors: Edward J. Lahoda, Peng Xu, Robert L. Oelrich, Jr., Hemant Shah, Jonathan Wright, Lu Cai
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Patent number: 11488730Abstract: 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: GrantFiled: October 7, 2020Date of Patent: November 1, 2022Assignee: Westinghouse Electric Company LLCInventors: Edward J. Lahoda, Peng Xu, Lu Cai
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Patent number: 11444263Abstract: 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: GrantFiled: October 12, 2019Date of Patent: September 13, 2022Assignees: 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
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Publication number: 20220084694Abstract: 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: ApplicationFiled: March 5, 2020Publication date: March 17, 2022Applicant: Westinghouse Electric Company LLCInventors: Edward J. LAHODA, Peng XU, Lu CAI, Yun LONG, John LYONS
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Publication number: 20220068511Abstract: 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: ApplicationFiled: September 13, 2021Publication date: March 3, 2022Applicant: Westinghouse Electric Company LLCInventors: Edward J. LAHODA, Peng XU, Robert L. OELRICH, JR., Hemant SHAH, Jonathan WRIGHT, Lu CAI
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Patent number: 11145425Abstract: 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: GrantFiled: January 29, 2019Date of Patent: October 12, 2021Assignee: Westinghouse Electric Company LLCInventors: Edward J. Lahoda, Peng Xu, Robert L. Oelrich, Jr., Hemant Shah, Jonathan Wright, Lu Cai
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Publication number: 20210020321Abstract: 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: ApplicationFiled: October 7, 2020Publication date: January 21, 2021Applicant: Westinghouse Electric Company LLCInventors: Edward J. LAHODA, Peng XU, Lu CAI
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Publication number: 20200365826Abstract: 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: ApplicationFiled: October 12, 2019Publication date: November 19, 2020Applicants: 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
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Patent number: 10803999Abstract: 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: GrantFiled: February 16, 2018Date of Patent: October 13, 2020Assignee: Westinghouse Electric Company LLCInventors: Edward J. Lahoda, Peng Xu, Lu Cai
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Publication number: 20200258642Abstract: 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: ApplicationFiled: February 12, 2019Publication date: August 13, 2020Applicant: WESTINGHOUSE ELECTRIC COMPANY, LLCInventors: PENG XU, LU CAI, SYLVESTER F. OGUNJI, EDWARD J. LAHODA, LARS HALLSTADIUS
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Publication number: 20200111584Abstract: 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: ApplicationFiled: November 27, 2019Publication date: April 9, 2020Applicant: WESTINGHOUSE ELECTRIC COMPANY LLCInventors: EDWARD J. LAHODA, HEMANT SHAH, PENG XU, LU CAI
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Publication number: 20190237206Abstract: 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: ApplicationFiled: January 29, 2019Publication date: August 1, 2019Applicant: WESTINGHOUSE ELECTRIC COMPANY LLCInventors: EDWARD J. LAHODA, PENG XU, ROBERT L. OELRICH, JR., HEMANT SHAH, JONATHAN WRIGHT, LU CAI
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Patent number: 10350856Abstract: 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: GrantFiled: November 2, 2017Date of Patent: July 16, 2019Assignee: Westinghouse Electric Company LLCInventors: Peng Xu, Lu Cai
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Publication number: 20190074095Abstract: 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: ApplicationFiled: September 5, 2017Publication date: March 7, 2019Applicant: WESTINGHOUSE ELECTRIC COMPANY, LLCInventors: EDWARD J. LAHODA, HEMANT SHAH, PENG XU, LU CAI
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Publication number: 20180268946Abstract: 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: ApplicationFiled: February 16, 2018Publication date: September 20, 2018Applicant: WESTINGHOUSE ELECTRIC COMPANY, LLCInventors: EDWARD J. LAHODA, PENG XU, LU CAI
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Publication number: 20180056628Abstract: 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: ApplicationFiled: November 2, 2017Publication date: March 1, 2018Applicant: WESTINGHOUSE ELECTRIC COMPANY LLCInventors: PENG XU, LU CAI
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Patent number: 9844923Abstract: 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: GrantFiled: August 14, 2015Date of Patent: December 19, 2017Assignee: Westinghouse Electric Company LLCInventors: Peng Xu, Lu Cai