Other

Korea Atomic Energy Research Institute

Lotte Chemical Corporation

Hyundai Motor Company

Korea Hydro Nuclear Power Co., Ltd.

Kia Motors Corporation

Duckil Industry Co., Ltd.

Myung Ho Lee

Sang Yoon Park

Yong Hwan Jeong

Jong Hyuk Baek

Byoung Kwon Choi

Cheol Nam

Youn Ho Jung

Kyeong Ho Kim

Jeong Yong Park

Sang Do Park

Jeong Min Cho

Gil Ju Kim

Jong Wook Lee

Dong Woo Jeong

Bong Soo Kim

Ji Ae Yong

Jun Yeol Heo

Jung Tae Kim

Jong Kweon Pyun

Hyun Gil Kim

Hak Gyun Kim

Choul Won So

Jun Hwan Kim

Younho Jung

Jong-Yun Kim

Jun Youp Kim

Joong Hyun Shin

Seung Su Han

Suk Bon Yoon

Dong Yeoul Kim

Yong-Joon Park

Yeong Uk Kim

Kwang-Yong Jee

Je Geon Bang

A bumper beam of a vehicle according to the present invention includes a pair of mounting portions for being fixed to a vehicle member, a supporting portion having a cross-section in which a front surface is closed and a rear surface opens and having both ends supporting the pair of mounting portions, a web disposed in front of the supporting portion, an energy absorbing portion supporting a rear surface of the web and supported by the front surface of the supporting portion to absorb energy generated when a colliding object collides to with the web, and an energy transmitting portion connecting the energy absorbing portion and the pair of mounting portions.

Bumper beam of vehicle

A bumper unit of a vehicle includes a plurality of bumper beams arranged in a width direction of the vehicle, each of the bumper beams being coupled at both ends thereof to a vehicle body, a bumper reinforcement member configured as a molded synthetic-resin base, the base being formed with a plurality of through-holes in the width direction of the vehicle such that the bumper beams penetrate the base via the through-holes, and a strengthening band formed of reinforcement fiber tows, the strengthening band being configured to surround the exterior of the bumper reinforcement member.

Bumper unit of vehicle and method for manufacturing the same

The present invention relates to a bumper system for a vehicle, and provides a bumper system for a vehicle, the system comprising: a bumper beam which has a fastening hole formed through each end thereof in the forward and backward direction; a crash box which is inserted into the fastening hole of the bumper beam; and a bracket which is fastened to the bumper beam so as to be able to prevent the crash box from being separated. Thereby, the system can meet both low speed crash regulations and RCAR performance.

Bumper system for vehicle

A switch apparatus for adjusting a power seat in a vehicle, may include a body, a plurality of switches installed on the body including a first switch manipulated in a horizontal direction, and a second switch spaced apart from the first switch and manipulated in a vertical direction, and a guide bracket, a first end portion of which is integrally coupled to the first switch and a second end portion of which is placed around the second switch and selectively coupled to the second switch according to a horizontal movement of the first switch, wherein the second switch is movable in the vertical direction while the first switch is in a neutral position, while the first switch is out of the neutral position, and wherein the second end portion of the guide bracket is interfered with the second switch while the second switch is out of a neutral position.

Switch apparatus for adjusting power seat in vehicle

A high Fe-containing zirconium composition having excellent corrosion resistance and a preparation method thereof. Specifically, disclosed are a high Fe-containing zirconium composition having excellent corrosion resistance and a preparation method thereof, the composition comprising: 0.5-1.0 wt % iron; 0.25-0.5 wt % chromium; 0.06-0.18 wt % oxygen; at least one element selected from the group consisting of 0.2-0.5 wt % tin, 0.1-0.3 wt % niobium and 0.05-0.3 wt % copper; and the balance of zirconium. The zirconium alloy has excellent corrosion resistance, and thus can be used as a material for nuclear fuel claddings, spacer grids and nuclear reactor core structures in light water reactor and heavy water reactor nuclear power plants.

High Fe contained zirconium alloy compositions having excellent corrosion resistance and preparation method thereof

Disclosed are mesoporous silica particles and a preparation method thereof, particularly, a method of preparing mesoporous silica particles, including mixing a silica precursor, an alkylamine-based surfactant, and a phosphoric acid-based cosurfactant, thus preparing a mixture solution (a mother liquor); adding or not adding the mixture solution with an acid solution, and conducting stirring, thus providing mesoporous silica particles; and thermally treating the mesoporous silica particles. These mesoporous silica particles are prepared using a phosphoric acid-based cosurfactant for stabilizing the surface of the particles to prevent the aggregation thereof, thereby uniformly distributing the particles. Through a hydrothermal reaction, the mesoporous silica particles have various pore sizes, a large surface area, and a high pore volume, and thus are widely used in catalysts, adsorbents, low dielectrics, and separation and purification processes, and are useful as templates for the preparation of novel porous materials, including porous carbon.

Mesoporous silica particles and preparation method thereof

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 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

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&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 cold-worked ingot at 440-600&deg; 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&times;10 hr or lower.

Method for manufacturing a tube and a sheet of niobium-containing zirconium alloy for a high burn-up nuclear fuel

Niobium-containing zirconium alloy for nuclear fuel claddings

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Daejeon, South Korea

Myung Ho Lee