Kepco Nuclear Co., Ltd.

Kepco Nuclear Fuel Co., Ltd.

Jung Cheol Shin

Yong Chan Kim

Sung Min Kim

Ki Bum Park

In Kyu Kim

Eun Hye Kim

Yong Shin Choi

Ho Yeon Hwang

Jin Man Joo

Jung Yoon Han

Sang Kyun Woo

Soon Ki Kim

Yong Gu Han

Chae Joon Lim

Dae Hee Kang

A gap control device for a Pilger die assembly of cold Pilger mills. The gap control device can independently control the height of a pair of bearing blocks which axially support an upper die. A lower plate has first and second receiving holes which respectively correspond to the upper portions of a pair of bearing blocks. First and second wedge plates are fitted into the receiving holes, and respectively have inclined surfaces on the upper portions thereof. First and second adjustment blocks respectively have inclined guide surfaces to be in surface contact with the inclined surfaces of the wedge plates, and are movable horizontally with respect to the lower plate. An upper plate is assembled to the upper portion of the lower plate to cover the adjustment blocks. First and second adjustment bolts allow the first and second adjustment blocks to be respectively manipulated in a horizontal direction.

Gap control device for pilger die assembly of cold pilger mills

Provided are a probe and an apparatus for measuring a thickness of an oxide layer of a fuel rod, capable of testing claddings of inner and outer fuel rods of a nuclear fuel assembly without disassembling the nuclear fuel assembly. The probe includes a fuel rod transfer region on which an eddy current sensor capable of continuously testing claddings of outer fuel rods of a fixed nuclear fuel assembly is mounted. Further, the apparatus includes a frame in which a cylinder driven in upward and downward directions is mounted, a first probe connected to one side of the cylinder in order to test claddings of outer fuel rods of a nuclear fuel assembly, and a second probe connected to the other side of the cylinder in order to test claddings of inner fuel rods of the nuclear fuel assembly.

Probe and apparatus for measuring thickness of oxide layer of fuel rod

Provided is an apparatus for measuring outer diameters of fuel rods of a nuclear fuel assembly, in which the fuel rods are standing upright and are used in a light water reactor. The apparatus includes a support unit fixed to a floor at a lower portion thereof so as to be kept insulated from vibrations caused by external forces, a measuring unit mounted on the support unit and moving up and down to measure the outer diameters of the fuel rods, and a transducer cooperating with the measuring unit, converting the measured outer diameters of the fuel rods into electrical signals, and sending the converted signals to the outside. Thus, the apparatus moves up and down to measure the outer diameters of the fuel rods, so that it can accurately check abnormalities in the outer diameters of the fuel rods.

Apparatus for measuring outer diameters of fuel rods of nuclear fuel assembly

Provided is an apparatus for measuring dimensions of a spacer grid for nuclear fuel assemblies. The apparatus includes a fixing unit fixed to a measuring table placed on a floor and kept insulated from vibrations caused by external force, a measuring unit mounted on the fixing unit and configured so that measuring members are installed on both sides of a rectangular spacer grid and move in forward and backward directions by cylinders while grasping the both sides of the spacer grid, and measure abnormalities in the both sides of the spacer grid, and a displacement measuring unit mounted on one side of the measuring unit and sending the measured abnormalities in the both sides of the spacer grid to the outside.

Apparatus for measuring dimensions of spacer grid for nuclear fuel assemblies

Growing community of inventors

Daejeon, South Korea

Jung Cheol Shin