Other

Korea Atomic Energy Research Institute

Korea Electric Power Corporation

Korea Institute of Machinery & Materials

Korea Hydro Nuclear Power Co., Ltd.

Silicon Works Co., Ltd.

Youn Ho Jung

Jong Hyuk Baek

Yong Hwan Jeong

Dong Seok Oh

Kyung Ho Yoon

Wang Kee In

Heung Seok Kang

Kee Nam Song

Kyeong Ho Kim

Sang Yoon Park

Hyung Kyu Kim

Myung Ho Lee

Jong Hun Kim

Yong-Jin Kim

Kun Woo Song

Joon-Yub Song

Dae Ho Kim

Hyun Gil Kim

Tae Hyun Chun

Byoung Kwon Choi

Cheol Nam

Byong Kwon Choi

Kwang Sun Choi

Il Hiun Kuk

Jae Ho Yang

Keon Sik Kim

Ki Won Kang

Jae-Hak Lee

Seung-Man Kim

Gyung Jin Park

Sun Jae Kim

Tae Soo Chun

Young Woo Rhee

Jae Woong Jung

Keenam Song

Heungseok Kang

Kyungho Yoon

Yongjin Kim

Taehyun Chun

Jun Hwan Kim

Dongseok Oh

Wangkee In

Sun-Jae Kim

Joonyub Song

Seung Man Kim

Jeong Yong Park

Yoon Sang Shin

Chang-Hwan Shin

Je Geon Bang

Jae-hak Lee

An orthodontic wire bending device includes a providing part, a bending unit and a cutting part. The providing part is configured to provide a wire. The bending unit is disposed at a front side of the providing part, and includes a fixing part and a bending part. The fixing part is configured to fix the wire. The bending part is configured to bend the wire fixed by the fixing part. The cutting part is configured to cut the wire bent by the bending part. The bending part includes a bending module, and the bending module is rotated along a circumferential direction or moves along a direction to make contact with at least one side of the wire for bending the wire.

Orthodontic wire bending device

In a system of manufacturing an orthodontic wire, a method for manufacturing the orthodontic wire using the system, and an orthodontic wire bending machine for performing the system, the system includes a teeth data obtaining part, a simulating part, a calculating part and a wire manufacturing part. The teeth data obtaining part obtains present teeth data of a patient. The simulating part generates final teeth data. The calculating part compares a predetermined threshold to a compared value between the present teeth data of the patient and the final teeth data. The wire manufacturing part selectively manufactures a wire for an orthodontic process or a wire for a dentition maintenance process based on a compared result of the calculating part.

System of manufacturing orthodontic wire, method for manufacturing the orthodontic wire using the same, and orthodontic wire bending machine for performing the same

A wire feeding unit includes a driving motor; a driving roller which rotates by a driving force of the driving motor; a plurality of driven rollers arranged such that outer circumferential surfaces thereof are positioned on a same line; a belt which interlocks the driving roller and the plurality of driven rollers and is brought into contact with a wire, which is drawn into a side of the driven rollers, on a side of the plurality of driven rollers; and a plurality of idlers which support the wire on a side in which the wire and the belt are in contact with each other and assist feeding of the wire along a feeding direction of the belt in a free-rotation state.

Wire feeding unit and wire bending apparatus including the same

The present disclosure allows increasing the sensing sensitivity or the perception rate for a hovering active pen using a threshold value.

Touch sensing device for sensing active pen and touch sensing system including the same

A method for fabricating a sintered duplex nuclear fuel pellet includes the steps of: preparing a first powder composed of a material selected from the group consisting of UOand UO&#x2014;ErO, and a second powder composed of UO&#x2014;GdOand a sintering additive; producing a duplex compact consisting of an annular outer portion composed of the first powder and a cylindrical inner portion composed of the second powder; and sintering the duplex compact under a reducing gas atmosphere, wherein the sintering additive contains manganese of 0.001% to 2% by weight based on the total weight of the cylindrical inner portion.

Fabrication method of sintered duplex nuclear fuel pellet

The present invention relates to a method for manufacturing zirconium-based alloys containing niobium with superior corrosion resistance for use in nuclear fuel rod claddings. The method of this invention comprises melting of the alloy, &#x3b2;-forging, &#x3b2;-quenching, hot-working, vacuum annealing, cold-working, intermediate annealing and final annealing, whereby the niobium concentration in the &#x3b1;-Zr matrix decreases from the supersaturation state to the equilibrium state to improve the corrosion resistance of the alloy. Such zirconium-based alloys containing niobium are usefully applied to nuclear fuel rod cladding of the cores in light water reactors and heavy water reactors.

Method for manufacturing zirconium-based alloys containing niobium for use in nuclear fuel rod cladding

The present invention relates to a nuclear fuel body comprising tungsten network and a method for manufacturing the same, more particularly, a nuclear fuel body in which tungsten network is continuously formed over the entire or some parts of a sintered body and a method for manufacturing the same. The sintered body in the nuclear fuel body of the present invention contains tungsten network having excellent heat conductivity, leading to the enhancement of heat conductivity of the nuclear fuel sintered body itself with decreasing the temperature of the nuclear fuel, so that it can contribute to the improvement in safety and performance of nuclear fuel.

Nuclear fuel body including tungsten network and method of manufacturing the same

The present invention relates to a zirconium alloy having excellent corrosion resistance and mechanical properties and a method for preparing a nuclear fuel cladding tube by zirconium alloy. More particulary, the present invention is directed to a zirconium alloy comprising Zr-aNb-bSn-cFe-dCr-eCu (a&equals;0.05-0.4 wt %, b&equals;0.3-0.7 wt %, c&equals;0.1-0.4 wt %, d&equals;0-0.2 wt % and e&equals;0.01-0.2 wt %, provided that Nb&plus;Sn&equals;0.35-1.0 wt %), and to a method for preparing a zirconium alloy nuclear fuel cladding tube, comprising melting a metal mixture comprising of the zirconium and alloying elements to obtain ingot, forging the ingot at &bgr; phase range, &bgr;-quenching the forged ingot at 1015-1075&deg; C., hot-working the quenched ingot at 600-650&deg; C., cold-working the hot-worked ingot in three to five passes, with intermediate vacuum annealing and final vacuum annealing the worked ingot at 460-540&deg; C., which can be applied to the core components in a light water and a heavy water atomic reactor type nuclear power plant.

Zirconium alloy having excellent corrosion resistance and mechanical properties for nuclear fuel cladding tube

A lips-type multi-purposed spacer grid for supporting fuel rods within a nuclear fuel assembly is disclosed. In the spacer grid, the fuel rods are in contact with dimples and water strider-type springs in an equiangular surface contact manner. The spacer grid distributes load, applied to the springs, to the entire structure of its inner strips, thus reducing peak stress at the contact surfaces between the fuel rods and the springs and diminishing vibration of the fuel rods, and thereby reducing possible fretting wear of the fuel rods due to hydraulic vibration of the fuel rods. The spacer grid also enlarges the allowable elastic range of the springs, and allows the springs to soundly support the fuel rods by using residual spring force. The spacer grid has mixing blades capable of minimizing pressure loss and flow interference, so that the fuel rod cooling efficiency of the nuclear fuel assembly is improved.

Lips-type multi-purposed nuclear fuel assembly spacer grid

A spacer grid used for placing and supporting fuel rods in nuclear reactor fuel assemblies is disclosed. The spacer grid of this invention has a plurality of grid springs designed to have an optimal shape of their vertical support parts, thus reducing fretting wear of the fuel rods caused by contact of the fuel rods with the grid springs. The grid spring has a vertical support part and a fuel rod support part. The vertical support part includes upper and lower base parts extending downward and upward from the central portions of the top and bottom edges of an opening formed at the central portion of a unit strip, and two bridge parts branched from the upper base part and extending symmetrically downward until they are united at the lower base part. The fuel rod support part includes a conformal support part brought into surface contact with the external surface of a fuel rod. Two transverse connection parts extend outward from the opposite outside edges of the conformal support part while being specifically bent, and are integrated with the central portions of the inside edges of the two bridge parts into a single structure, thus connecting the fuel rod support part to the vertical support part.

Spacer grid for nuclear reactor fuel assemblies with grid springs maintaining conformal contact with fuel rods and enlarged elastic range

Zirconium alloy having high corrosion resistance and high strength

A nuclear fuel spacer grid, fabricated by intersecting a plurality of grid strips and used for placing and supporting a plurality of elongated fuel rods within a nuclear fuel assembly, is disclosed. The spacer grid of this invention has a plurality of dimple vanes on its grid strips. The dimple vanes are designed to guide the coolant from one cell to neighboring cells of the spacer grid, thus accomplishing a desired coolant mixing effect and increasing the thermal allowance of the fuel rods and accomplishing a high performance fuel assembly. The spacer grid also has a multi-spring structure, consist in of one arc-shaped main spring and two bow-shaped sub-springs. The main spring directly supports the fuel rod within the spacer grid, while the sub-springs have the same radius of curvature as that of the external surface of the fuel rod and effectively support the fuel rod when the main spring fails to support the fuel rod. The spacer grid of this invention thus accomplishes desired soundness of the fuel rods within the fuel assembly during an expected life span of the fuel rods.

Spacer grid with multi-springs and dimple vanes for nuclear fuel assemblies

Niobium-containing zirconium alloy for nuclear fuel claddings

A spacer grid with H-springs for use in a nuclear reactor fuel assembly is disclosed. In the spacer grid, two sets of intersectional grid strips are arranged in sets at an angle to each other prior to being encircled by a plurality of perimeter strips, thus forming a plurality of four-walled cells individually placing and supporting an elongated fuel rod therein. A plurality of regularly spaced openings are formed on each of the grid strips and perimeter strips at portions corresponding to the cells. An H-shaped spring is set in each of the openings and has a specifically curved rib capable of being brought into conformal surface contact with a fuel rod placed in each of the cells. The H-shaped spring thus elastically supports the fuel rod. Two positioning dimples are provided on each of the strips at positions above and below each of the openings. The two positioning dimples are so specifically curved as to come into conformal surface contact with a fuel rod, thus elastically supporting the fuel rod in cooperation with the H-shaped springs.

Spacer grid with H-spring for fuel rods for use in nuclear reactor fuel

Growing community of inventors

Daejeon, South Korea

Youn Ho Jung