Patents by Inventor Younho Jung

Younho Jung 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: 6845138
    Abstract: A spacer grid with hybrid flow-mixing devices for nuclear fuel bundle is made up of an intersection of a plurality of thin straps at right angles to form a plurality of cells for receiving and supporting fuel rods. Each strap is composed of two types of strap units, called a primary strap unit and a secondary strap unit, which are alternately arranged along the strap. The primary strap unit is a strap section having a primary vane set, and a secondary strap unit is a strap section having a secondary vane set. The straps intersect such that, by primary and secondary strap units, each intersection forms a hybrid flow-mixing device around the top of each junction. The primary vane set, consisting of a trapezoidal primary vane stand and two bent primary mixing vanes on both sides, protrudes upwardly from the strap and is primarily for generating cross flow between channels.
    Type: Grant
    Filed: August 7, 2002
    Date of Patent: January 18, 2005
    Assignees: Korea Atomic Energy Research Institute, Korea Hydro & Nuclear Power Co., Ltd.
    Inventors: Taehyun Chun, Dongseok Oh, Wangkee In, Keenam Song, Hyungkyu Kim, Heungseok Kang, Kyungho Yoon, Younho Jung
  • Patent number: 6721384
    Abstract: A spacer grid for nuclear fuel assemblies is disclosed. This spacer grid has a plurality of side weld supports, that is, main supports, upper sub-supports and lower sub-supports, on its interlaced inner straps, with two flow mixing vanes integrally extending upward from each of the main supports. This spacer grid is fabricated by seam-welding the interlaced first and second inner straps to each other along the upper axial junction lines of the crossing main and upper sub-supports at the top of the intersections, and along the lower axial junction lines of the crossing lower sub-supports at the bottom of the intersections, thus forming side weld lines at the intersections.
    Type: Grant
    Filed: October 25, 2002
    Date of Patent: April 13, 2004
    Assignees: Korea Atomic Energy Research Institute, Korea Hydro & Nuclear Power Co., Ltd.
    Inventors: Dongseok Oh, Taehyun Chun, Wangkee In, Keenam Song, Hyungkyu Kim, Heungseok Kang, Kyungho Yoon, Younho Jung
  • Patent number: 6714619
    Abstract: A spacer grid for use in a nuclear fuel assembly has double-deflected vanes that guide an axial flow of coolant around fuel rods and thereby generate swirl flow. The vanes each have a double bend projecting upwardly from first inner straps and projecting toward one fuel rod. The vanes are sufficiently wide at their bases to prevent inadvertent deformation due to contact with fuel rods during an insertion of fuel rods into the cells. The vanes also make a smooth variation in the cross-sectional area of the coolant channel at the outlet of the spacer grid, thus reducing a loss of pressure during reactor operation.
    Type: Grant
    Filed: August 7, 2002
    Date of Patent: March 30, 2004
    Assignees: Korea Atomic Energy Research Institute, Korea Kydro & Nuclear Power Co., Ltd.
    Inventors: Dongseok Oh, Taehyun Chun, Wangkee In, Keenam Song, Hyungkyu Kim, Heungseok Kang, Kyungho Yoon, Younho Jung
  • Publication number: 20040005025
    Abstract: A spacer grid for use in a nuclear fuel assembly has double-deflected vanes that guide an axial flow of coolant around fuel rods and thereby generate swirl flow. The vanes each have a double bend projecting upwardly from first inner straps and projecting toward one fuel rod. The vanes are sufficiently wide at their bases to prevent inadvertent deformation due to contact with fuel rods during an insertion of fuel rods into the cells. The vanes also make a smooth variation in the cross-sectional area of the coolant channel at the outlet of the spacer grid, thus reducing a loss of pressure during reactor operation.
    Type: Application
    Filed: August 7, 2002
    Publication date: January 8, 2004
    Inventors: Dongseok Oh, Taehyun Chun, Wangkee In, Keenam Song, Hyungkyu Kim, Heungseok Kang, Kyungho Yoon, Younho Jung
  • Publication number: 20030138073
    Abstract: A spacer grid for nuclear fuel assemblies is disclosed. This spacer grid has a plurality of side weld supports, that is, main supports, upper sub-supports and lower sub-supports, on its interlaced inner straps, with two flow mixing vanes integrally extending upward from each of the main supports. This spacer grid is fabricated by seam-welding the interlaced first and second inner straps to each other along the upper axial junction lines of the crossing main and upper sub-supports at the top of the intersections, and along the lower axial junction lines of the crossing lower sub-supports at the bottom of the intersections, thus forming side weld lines at the intersections.
    Type: Application
    Filed: October 25, 2002
    Publication date: July 24, 2003
    Inventors: Dongseok Oh, Taehyun Chun, Wangkee In, Keenam Song, Hyungkyu Kim, Heungseok Kang, Kyungho Yoon, Younho Jung
  • Publication number: 20030053584
    Abstract: A spacer grid with hybrid flow-mixing devices for nuclear fuel bundle is made up of an intersection of a plurality of thin straps at right angles to form a plurality of cells for receiving and supporting fuel rods. Each strap is composed of two types of strap units, called a primary strap unit and a secondary strap unit, which are alternately arranged along the strap. The primary strap unit is a strap section having a primary vane set, and a secondary strap unit is a strap section having a secondary vane set. The straps intersect such that, by primary and secondary strap units, each intersection forms a hybrid flow-mixing device around the top of each junction. The primary vane set, consisting of a trapezoidal primary vane stand and two bent primary mixing vanes on both sides, protrudes upwardly from the strap and is primarily for generating cross flow between channels.
    Type: Application
    Filed: August 7, 2002
    Publication date: March 20, 2003
    Inventors: Taehyun Chun, Dongseok Oh, Wangkee In, Keenam Song, Hyungkyu Kim, Heungseok Kang, Kyungho Yoon, Younho Jung
  • Patent number: 6514360
    Abstract: Disclosed is a method for manufacturing a tube and a sheet of niobium-containing zirconium alloys for the high burn-up nuclear fuel. The method comprises melting Nb-added zirconium alloy to ingot; forging the ingot at &bgr; phase range; &bgr;-quenching the forged ingot after solution heat-treatment at 1015-1075° C.; hot-working the quenched ingot at 600-650° C.; cold-working the hot-worked ingot in three to five passes, with intermediate vacuum annealing; and final vacuum annealing the cold-worked ingot at 440-600° C., wherein temperatures of intermediate vacuum annealing and final vacuum annealing after &bgr;-quenching are changed so as to attain the condition under which precipitates in the alloy matrix are limited to an average diameter of 80 nm or smaller and the accumulated annealing parameter (&Sgr; A) is limited to 1.0×10−18 hr or lower.
    Type: Grant
    Filed: May 10, 2001
    Date of Patent: February 4, 2003
    Assignees: Korea Atomic Energy Reserach Institute, Korea Electric Power Corporation
    Inventors: Yong Hwan Jeong, Jong Hyuk Baek, Byoung Kwon Choi, Kyeong Ho Kim, Myung Ho Lee, Sang Yoon Park, Cheol Nam, Younho Jung
  • Publication number: 20020136347
    Abstract: Disclosed is a method for manufacturing a tube and a sheet of niobium-containing zirconium alloys for the high burn-up nuclear fuel. The method comprises melting Nb-added zirconium alloy to ingot; forging the ingot at &bgr; phase range; &bgr;-quenching the forged ingot after solution heat-treatment at 1015-1075° C.; hot-working the quenched ingot at 600-650° C.; cold-working the hot-worked ingot in three to five passes, with intermediate vacuum annealing; and final vacuum annealing the cold-worked ingot at 440-600° C., wherein temperatures of intermediate vacuum annealing and final vacuum annealing after &bgr;-quenching are changed so as to attain the condition under which precipitates in the alloy matrix are limited to an average diameter of 80 nm or smaller and the accumulated annealing parameter (&Sgr;A) is limited to 1.
    Type: Application
    Filed: May 10, 2001
    Publication date: September 26, 2002
    Inventors: Yong Hwan Jeong, Jong Hyuk Baek, Byoung Kwon Choi, Kyeong Ho Kim, Myung Ho Lee, Sang Yoon Park, Cheol Nam, Younho Jung