Patents by Inventor Yuriy Aleshin

Yuriy Aleshin 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).

  • Patent number: 10872701
    Abstract: The invention relates to a multi-component cladding for a nuclear fuel rod that includes a combination of ceramic and metal components. More particularly, the invention is directed to a cladding that includes a ceramic composite having a zirconium composition deposited thereon to form a zirconium coated ceramic composite. The ceramic composite includes a ceramic matrix and a plurality of ceramic fibers. The cladding is effective to protect the contents of the cladding structure from exposure to high temperature environments during various load conditions of a nuclear reactor.
    Type: Grant
    Filed: June 10, 2016
    Date of Patent: December 22, 2020
    Assignee: Westinghouse Electric Company LLC
    Inventors: Yuriy Aleshin, Joonhyung Choi
  • Publication number: 20200373025
    Abstract: A filtering arrangement for use in a bottom nozzle of a fuel assembly in a nuclear reactor includes a top surface, a bottom surface, a plurality of vertical wall portions arranged in a generally squared grid-like pattern which extend between the bottom surface and the top surface and define a plurality of non-circular passages extending between the bottom surface and the top surface through the arrangement, and a plurality of first debris filters which are each positioned between the top surface and the bottom surface to generally span across a respective one of the plurality of passages.
    Type: Application
    Filed: May 22, 2019
    Publication date: November 26, 2020
    Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
    Inventors: ARTEM ALESHIN, YURIY ALESHIN
  • Patent number: 10818401
    Abstract: A spring apparatus in accordance with the disclosed and claimed concept is usable in a nuclear installation. In one embodiment, the spring apparatus includes a plurality of springs that are in a compressed state and that are compressively engaged with an upper core plate of a nuclear reactor when the reactor is in a cold condition. However, when the reactor is in a hot condition, a spring of the plurality of springs is in a free state wherein a free end of the spring is in an uncompressed state and is disengaged from the upper core plate. In another embodiment, the spring apparatus employs a support apparatus that is also in accordance with the disclosed and claimed concept and that includes one or more bumpers that engage the springs of a spring pack from the underside.
    Type: Grant
    Filed: February 2, 2016
    Date of Patent: October 27, 2020
    Assignee: Westinghouse Electric Company LLC
    Inventors: Joonhyung Choi, Yuriy Aleshin
  • Publication number: 20200043617
    Abstract: A nuclear fuel assembly comprising a plurality of control rod guide assemblies. At least one of the control rod guide assemblies includes a guide tube having an axial dimension, the guide tube being supported by the plurality of grids and extending axially between the top nozzle and the bottom nozzle, the guide tube having an upper portion having a first radius and a lower portion having a second radius less than the first radius, and an external dashpot tube disposed around a portion of the lower portion in an area beginning at the bottom grid and extending toward the top nozzle.
    Type: Application
    Filed: September 3, 2019
    Publication date: February 6, 2020
    Applicant: WESTINGHOUSE ELECTRIC COMPANY, LLC
    Inventors: YURIY ALESHIN, BRIAN MILLARE, MICHAEL O. BAUSCH, CARTER ELIOT LUNDE
  • Patent number: 10446277
    Abstract: A nuclear fuel assembly comprising a plurality of control rod guide assemblies. At least one of the control rod guide assemblies includes a guide tube having an axial dimension, the guide tube being supported by the plurality of grids and extending axially between the top nozzle and the bottom nozzle, the guide tube having an upper portion having a first radius and a lower portion having a second radius less than the first radius, and an external dashpot tube disposed around a portion of the lower portion in an area beginning at the bottom grid and extending toward the top nozzle.
    Type: Grant
    Filed: January 12, 2017
    Date of Patent: October 15, 2019
    Assignee: Westinghouse Electric Company LLC
    Inventors: Yuriy Aleshin, Brian Millare, Michael O. Bausch, Carter Eliot Lunde
  • Publication number: 20180197640
    Abstract: A nuclear fuel assembly comprising a plurality of control rod guide assemblies. At least one of the control rod guide assemblies includes a guide tube having an axial dimension, the guide tube being supported by the plurality of grids and extending axially between the top nozzle and the bottom nozzle, the guide tube having an upper portion having a first radius and a lower portion having a second radius less than the first radius, and an external dashpot tube disposed around a portion of the lower portion in an area beginning at the bottom grid and extending toward the top nozzle.
    Type: Application
    Filed: January 12, 2017
    Publication date: July 12, 2018
    Applicant: WESTINGHOUSE ELECTRIC COMPANY, LLC
    Inventors: YURIY ALESHIN, BRIAN MILLARE, MICHAEL O. BAUSCH, CARTER ELIOT LUNDE
  • Publication number: 20170358372
    Abstract: The invention relates to a multi-component cladding for a nuclear fuel rod that includes a combination of ceramic and metal components. More particularly, the invention is directed to a cladding that includes a ceramic composite having a zirconium composition deposited thereon to form a zirconium coated ceramic composite. The ceramic composite includes a ceramic matrix and a plurality of ceramic fibers. The cladding is effective to protect the contents of the cladding structure from exposure to high temperature environments during various load conditions of a nuclear reactor.
    Type: Application
    Filed: June 10, 2016
    Publication date: December 14, 2017
    Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
    Inventors: YURIY ALESHIN, JOONHYUNG CHOI
  • Publication number: 20170221591
    Abstract: A spring apparatus in accordance with the disclosed and claimed concept is usable in a nuclear installation. In one embodiment, the spring apparatus includes a plurality of springs that are in a compressed state and that are compressively engaged with an upper core plate of a nuclear reactor when the reactor is in a cold condition. However, when the reactor is in a hot condition, a spring of the plurality of springs is in a free state wherein a free end of the spring is in an uncompressed state and is disengaged from the upper core plate. In another embodiment, the spring apparatus employs a support apparatus that is also in accordance with the disclosed and claimed concept and that includes one or more bumpers that engage the springs of a spring pack from the underside.
    Type: Application
    Filed: February 2, 2016
    Publication date: August 3, 2017
    Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
    Inventors: JOONHYUNG CHOI, YURIY ALESHIN
  • Patent number: 8842796
    Abstract: A method of detecting defects in nuclear fuel within a fuel rod that first heats the fuel rod to a temperature substantially above the ambient temperature. The surface temperature of the fuel rod cladding is then monitored as the fuel rod is allowed to cool. Variations in the temperature measured over the surface is then noted as an indication of defects.
    Type: Grant
    Filed: November 22, 2011
    Date of Patent: September 23, 2014
    Assignee: Westinghouse Electric Company LLC
    Inventors: Yuriy Aleshin, David B. Mitchell
  • Patent number: 8666018
    Abstract: A nuclear fuel rod plenum spring assembly that has a spacer affixed to the lower end of the ground torsion spring. The spacer has a substantially flat surface on its underside that presses against the upper surface of the upper fuel pellets to spread the load of the spring over the top surface of the upper most fuel pellet.
    Type: Grant
    Filed: January 6, 2011
    Date of Patent: March 4, 2014
    Assignee: Westinghouse Electric Company LLC
    Inventors: Yuriy Aleshin, Stephen H. Green, Andrew Atwood, Hemant Shah
  • Patent number: 8594269
    Abstract: The present invention provides novel fuel assemblies for use with PWR nuclear reactors and power plants, and in particular, VVER nuclear reactors. The fuel assemblies offer enhanced structural stability, skeletal rigidity, and distortion (bow and twist) resistance to support high burn-up fuel management. Each fuel assembly may include a plurality of fuel rods, a plurality of control rods and guide thimbles, at least one instrumentation tube, and a plurality of grids. At least one fuel rod is replaced with a structural support replacement rod made from zirconium (Zr) alloy, stainless steel, or any other suitable material. The structural support replacement rod may be hollow or solid. The structural support replacement rods are preferably disposed at or about the periphery, and in some cases, the corners of the geometric array, which is preferably a hexagon or square.
    Type: Grant
    Filed: January 13, 2006
    Date of Patent: November 26, 2013
    Assignee: Westinghouse Electric Company LLC
    Inventors: Yuriy Aleshin, James A. Sparrow, Keith J. Drudy
  • Publication number: 20130129029
    Abstract: A method of detecting defects in nuclear fuel within a fuel rod that first heats the fuel rod to a temperature substantially above the ambient temperature. The surface temperature of the fuel rod cladding is then monitored as the fuel rod is allowed to cool. Variations in the temperature measured over the surface is then noted as an indication of defects.
    Type: Application
    Filed: November 22, 2011
    Publication date: May 23, 2013
    Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
    Inventors: Yuriy Aleshin, David B. Mitchell
  • Publication number: 20120263271
    Abstract: A nuclear fuel pellet design that is a cylindrical axial profile with either a larger radius or conical shaped ends such that the as built diameter at the ends of the pellet are slightly smaller than at the middle and at normal operating conditions, the diameter at the ends is nearly the same as at the middle. Preferably, there are short chamfers at the axial ends of the pellet.
    Type: Application
    Filed: April 14, 2011
    Publication date: October 18, 2012
    Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
    Inventors: Yuriy Aleshin, David B. Mitchell
  • Publication number: 20120177170
    Abstract: A nuclear fuel rod plenum spring assembly that has a spacer affixed to the lower end of the ground torsion spring. The spacer has a substantially flat surface on its underside that presses against the upper surface of the upper fuel pellets to spread the load of the spring over the top surface of the upper most fuel pellet.
    Type: Application
    Filed: January 6, 2011
    Publication date: July 12, 2012
    Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC
    Inventors: Yuriy Aleshin, Stephen H. Green, Andrew Atwood, Hemant Shah
  • Publication number: 20110164719
    Abstract: A debris filter bottom nozzle for a pressurized water nuclear reactor fuel assembly that employs a corrugated screen in combination with flow through holes in an adapter plate to filter out potentially damaging debris. The area between the screen and the adapter plate defines a plenum that forms a collection point for the debris and coolant access is provided to the plenum through openings in the screen and sidewalls of the nozzle.
    Type: Application
    Filed: January 5, 2010
    Publication date: July 7, 2011
    Applicant: Westinghouse Electric Company, LLC
    Inventor: Yuriy Aleshin
  • Patent number: 7668284
    Abstract: A nuclear fuel assembly having a tube-in-tube control rod guide tube design that incorporates an end plug that extends axially upward to an elevation above the lower most grid where it is sealed at its upper end to the lower end of the control rod guide tube. The guide tube lower end plug has a threaded recess in its upper surface that mates with a corresponding dashpot end plug threaded extension that is formed as an insert in the lower end of the guide tube. A hole formed through the outer wall of the guide tube end plug at the elevation of the lower portion of the recess provides a positive inspection port for assuring the proper seating of the dashpot. A method of manufacture of such a fuel assembly is also disclosed.
    Type: Grant
    Filed: December 11, 2008
    Date of Patent: February 23, 2010
    Assignee: Westinghouse Electric Co. LLC
    Inventors: James A. Sparrow, Yuriy Aleshin, Garry C. Crabtree
  • Publication number: 20090252281
    Abstract: A nuclear fuel assembly having a tube-in-tube control rod guide tube design that incorporates an end plug that extends axially upward to an elevation above the lower most grid where it is sealed at its upper end to the lower end of the control rod guide tube. The guide tube lower end plug has a threaded recess in its upper surface that mates with a corresponding dashpot end plug threaded extension that is formed as an insert in the lower end of the guide tube. A hole formed through the outer wall of the guide tube end plug at the elevation of the lower portion of the recess provides a positive inspection port for assuring the proper seating of the dashpot. A method of manufacture of such a fuel assembly is also disclosed.
    Type: Application
    Filed: December 11, 2008
    Publication date: October 8, 2009
    Applicant: Westinghouse Electric Company, LLC
    Inventors: James A. Sparrow, Yuriy Aleshin, Garry C. Crabtree
  • Patent number: 7515674
    Abstract: A nuclear fuel assembly having a tube-in-tube control rod guide tube design that incorporates an end plug that extends axially upward to an elevation above the lower most grid where it is sealed at its tipper end to the lower end of the control rod guide tube. The guide tube lower end plug has a threaded recess in its upper surface that mates with a corresponding dashpot end plug threaded extension that is formed as an insert in the lower end of the guide tube. A hole formed through the outer wall of the guide tube end plug at the elevation of the lower portion of the recess provides a positive inspection port for assuring the proper seating of the dashpot. A method of manufacture of such a fuel assembly is also disclosed.
    Type: Grant
    Filed: October 18, 2006
    Date of Patent: April 7, 2009
    Assignee: Westinghouse Electric Co LLC
    Inventors: James A. Sparrow, Yuriy Aleshin, Garry C. Crabtree
  • Publication number: 20080137798
    Abstract: A nuclear fuel assembly having a tube-in-tube control rod guide tube design that incorporates an end plug that extends axially upward to an elevation above the lower most grid where it is sealed at its tipper end to the lower end of the control rod guide tube. The guide tube lower end plug has a threaded recess in its upper surface that mates with a corresponding dashpot end plug threaded extension that is formed as an insert in the lower end of the guide tube. A hole formed through the outer wall of the guide tube end plug at the elevation of the lower portion of the recess provides a positive inspection port for assuring the proper seating of the dashpot. A method of manufacture of such a fuel assembly is also disclosed.
    Type: Application
    Filed: October 18, 2006
    Publication date: June 12, 2008
    Applicant: Westinghouse Electric Company, LLC
    Inventors: James A. Sparrow, Yuriy Aleshin, Garry C. Crabtree
  • Publication number: 20080084957
    Abstract: A nuclear fuel assembly having improved dimensional stability to support aggressive fuel management wherein the fuel skeleton lateral stiffness is enhanced by the addition of a second joint attachment between the control rod guide thimble and spacer grid support sleeve.
    Type: Application
    Filed: October 6, 2006
    Publication date: April 10, 2008
    Applicant: Westinghouse Electric Company, LLC
    Inventors: Yuriy Aleshin, James A. Sparrow