Abstract: The present invention relates to a remote meter reading system using a grouped data structure. The central processing unit of the electronic electric power meter collects the data having similar function and groups the same. Each group is classified into main items, and each main item is classified into sub-items and is stored in the memory apparatus, and when a data transmission request signal of the wired and wireless meter reading terminal and the remote meter reading server is inputted in accordance with a data address system corresponding to a grouped data stored in the memory apparatus, a collecting data corresponding to the data address system that the data transmission request signal represents is selected, and is transmitted to the wired and wireless meter reading terminal and the remote meter reading server, respectively.

Abstract: A strain measurement system includes a tunable light generator, a coupler, a fiberoptic sensor unit, and an optical detector. The tunable light generator includes a Super Luminescent light emission Diode (SLD), and a tunable Fabry-Perrot (FP) filter cascaded to an output terminal of the SLD to convert light having a wideband spectrum into discrete optical signals. The coupler receives and distributes the optical signals and passes them to a wavelength compensation device which detects wavelengths of the optical signals. The fiberoptic sensor unit receives the optical signals from the tunable light generator through the coupler and transmits a response signal corresponding to a variation of strain attributable to load. The optical detector detects the response signal output from the fiberoptic sensor through the coupler.

Abstract: Disclosed herein are a high-sensitivity method and apparatus for monitoring the concentration or inflow of impurities in circulating water of a circulating water system, which can remarkably improve the measurement sensitivity by converting carbonate ions of low conductivity into chlorine or sulfate ions of increased conductivity, and which can measure the inflow of air or organic substances and the amount of inflow in a simple and efficient manner in real-time. The method of the present invention comprises the steps of: increasing a content of strong acids in sample water and thus increasing equivalent conductivity of the impurities, by utilizing cation exchange resin together with anion exchange resin, in which cations of the sample water are adsorbed on the cation exchange resin to form strong acids while weakly acidic anions of low dissociation degree in the sample water are adsorbed on the anion exchange resin to form strong acids; and measuring the increased conductivity of the impurities.

Abstract: The present invention provides a method of processing organic waste (D) in divided solid and/or liquid form, the method being implemented in a single reactor (1) containing a bath of molten glass (V) surmounted by a gas phase (G), the method comprising incinerating said waste (D) in the presence of oxygen at the surface (S) of said bath of molten glass (V), and in vitrifying said incinerated waste (D) in said bath of molten glass (V). In said method, and in characteristic manner, in addition to the oxygen delivered as oxidizer into said gas phase (G), oxygen is also injected into said bath of molten glass (V) in a quantity that is sufficient to minimize or to avoid any formation of metal within said bath of glass (V); advantageously in a quantity that is sufficient to minimize or to avoid any formation of metal within said bath of glass (V) and also to subject said bath of glass (V) to moderate stirring.

Abstract: A static excitation system that can eliminate shaft vibrations of a generator and overvoltage when it is underexited is provided. The static excitation system includes an initial excitation equipment; a step-down transformer; a 3-phase diode bridge; a boost chopper provided with a transistor and a resister, and maintaining DC voltage to be constant; a DC chopper provided with a plurality of transistors and diodes, and supplying DC power to a rotor of a generator; a boost controller for controlling the boost chopper; and a DC chopper controller for controlling the DC chopper, wherein, overvoltage applied on the excitation system when underexcited is eliminated owing to the boost chopper preventing any changes at an output terminal of the generator from being transferred to the excitation system, and maintaining the excitation DC voltage to be constant; and also owing to the DC chopper which is capable of 4 quadrant operation, hereby pole slipping of the generator can be prevented.

Abstract: A double strip mixing grid for nuclear reactor fuel assemblies is disclosed. This grid is fabricated by intersecting at right angles a plurality of double strips, each fabricated by welding two thin sheets together into a single structure with coolant channels. The mixing grid, having the channels, effectively mixes low temperature coolant with high temperature coolant within a fuel assembly, thus improving the thermal efficiency of the fuel assemblies. This mixing grid also effectively prevents the coolant from being partially overheated, thus improving the soundness of nuclear reactors. This mixing grid also has swirling flow blades and/or lateral flow blades to further improve the thermal efficiency of the fuel assembly. This mixing grid elastically supports the fuel rods by the sheets of the double strips, collaterally acting as positioning springs.

Abstract: A remote-controlled mobile cleaning device for removal and collection of high radioactive waste debris in a spent nuclear fuel process and fabrication area, such as a hot-cell, is disclosed. The device includes navigation means for moving it to the desired cleaning location and climbing over such obstacles as electrical cables and pneumatic tubes placed on the hot-cell floor to be cleaned, suction and collection means for dislodging, filtering, and capturing high radioactive waste debris, and cover means for protecting suction and collection means. The device that is operated by remote control cleans and collects loose dry spent nuclear fuel powder and other high-radioactive waste debris adhered to both the contaminated in-cell floor and the in-cell spent nuclear fuel process and fabrication equipment, without spreading inside the hot-cell.

Abstract: A single cell and stack structure for SOFC stacks is disclosed. The single cell consists of a fuel electrode, an electrolyte and an air electrode, with opposite two or four sides of said single cell is shaped while being bent downwardly, thus forming an electrode support type structure or a self-support (electrolyte support) type structure each having a reversed U-shaped cross-section. In the SOFC stack structure, electrode support type or self-support type single cells are gastightly stacked on a separating plate while being held on a plurality of sealing grooves sealed with sealant. In the SOFC stack, the fuel gas and the oxidizing gas are free from being mixed together due to an improved gas sealing structure. The SOFC stack is thus free from a stress due to a difference in coefficient of thermal expansion between the single cells and the separating plate at a raised or lowered temperature.

Abstract: Disclosed are a power automation system using a TRS network and a control method thereof which can reduce the power failure time and power failure areas when an obstacle is raised by providing a pure radio transmission path using a TRS network, in which base transceiver subsystems mostly stand on an eminence and a high output service can be provided, between a control center computer and power equipment so that the remote control center computer can promptly control the power equipment and the obstacle raised in the power equipment.

Abstract: A duct-type spacer grid for nuclear fuel assemblies is disclosed. In this spacer grid, a plurality of duct-shaped grid elements, individually having an octagonal cell, are closely arranged in parallel and are welded together, thus forming a matrix structure. The grid elements do not pass across the center of the subchannel of the assembly, thus effectively reducing pressure loss. Each of the grid elements is formed as an independent cell, and so they effectively resist against a lateral impact. A plurality of integral type swirl flow vanes, having different heights or same height, axially extend from the top of the grid to be positioned within each subchannel. The swirl flow vanes are bent outwardly, and so they do not contact the fuel rods during an insertion of the fuel rods into the cells. In the spacer grid, the fuel rods are supported within the cells by line contact springs without using any dimple.

Abstract: The present invention provides a method of processing organic waste (D) in divided solid and/or liquid form, the method being implemented in a single reactor (1) containing a bath of molten gas (V) surmounted by a gas phase (G), the method comprising incinerating said waste (D) in the presence of oxygen at the surface (S) of said bath of molten glass (V), and vitrifying said incinerated waste (D) in said bath of molten glass (V). In characteristic manner, in said method, said waste (D) is introduced into said reactor (1) in association with dual cooling; the device (5) for feeding said reactor (1) with said waste (D) is cooled on its side adjacent to the gas phase (G), advantageously by the circulation of at least one is cooling fluid maintained at a temperature higher than the dew point of said gas phase (G), and it is also cooled, advantageously independently, on its side adjacent to the incoming waste (D).

Abstract: The present invention relates to a method for inhibiting stress corrosion cracking occurring on steam generator tubes in the secondary side of nuclear power plants and an inhibitor therefor. The method comprises supplying cerium boride as an inhibitor for stress corrosion cracking into the secondary feed water of the nuclear power plants. The method according to the present invention improves resistance of stress corrosion cracking three times or higher than no inhibitor, and two times or higher than the conventional inhibitor. In particular, the method according to the present invention shows a superior inhibiting effect in the lead-contaminated environment such that the complete inhibition of stress corrosion cracking can be achieved. As thus, the method can reduce the unexpected stop of operating nuclear power plants caused by the stress corrosion cracking on steam generator tubes, thereby reducing the cost required for maintaining and repairing the tubes.

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.

Abstract: A fuel rod extracting machine which can extract the fuel rods one by one from a Korean type 17×17 Light Water Reactor fuel assembly comprises a multi-functional rotary head including a camera for measuring the positions of the fuel rods and securing nuts being fastened on the bottom end piece of fuel assembly, an impact wrench for unfastening the securing nuts, and a gripper for gripping and extracting the fuel rods one by one. All of these are installed on a single rotary disc, which is driven by a tool rotating motor, at intervals of 90 degrees. To improve the reliability and safety in using the multi-functional rotary head, a load cell and a remote compliance center are installed at the rear of the gripper. The load cell monitors a state of insertion of the fuel rod into a collet and measures a fuel rod extracting force. The remote compliance center provides the smooth insertion of the fuel rod onto the collet, even though there exists a small misalignment between them.

Abstract: A nuclear fuel spacer grid, fabricated by intersecting a plurality of zircaloy or inconel grid strips and used for placing and supporting a plurality of elongated fuel rods within a nuclear fuel assembly, is disclosed. In the spacer grid of this invention, each of the grid strips is not cut away to form separate springs or dimples for supporting the fuel rods, but has an axial slot extending from one end of each strip to a length. The grid strips are intersected at the slots prior to being welded together into a single grid structure at a welding tap formed at an outside end or a middle portion of each of the slots. Each of the grid strips also has a dipper-shaped coolant mixing vane, or a dipper vane, at each of the upper and lower ends thereof. The spacer grid thus maximizes the thermal hydraulic coolant mixing effect within a fuel assembly and stably supports the fuel rods within the assembly while improving the mechanical/structural strength of the assembly, such as a buckling strength.

Abstract: A duct-type spacer grid for nuclear fuel assemblies is disclosed. In this spacer grid, a plurality of duct-shaped grid elements, individually having an octagonal cell, are closely arranged in parallel and are welded together, thus forming a matrix structure. The grid elements do not pass across the center of the subchannel of the assembly, thus effectively reducing pressure loss. Each of the grid elements is formed as an independent cell, and so they effectively resist against a lateral impact. A plurality of integral type swirl flow vanes, having different heights or same height, axially extend from the top of the grid to be positioned within each subchannel. The swirl flow vanes are bent outwardly, and so they do not contact the fuel rods during an insertion of the fuel rods into the cells. In the spacer grid, the fuel rods are supported within the cells by line contact springs without using any dimple.

Abstract: A dissolved oxygen removal method using an activated carbon fiber catalyst thereof which includes the steps of a reducing agent injection step for injecting a reducing agent into the water, a reactor entrance dissolved oxygen measuring step for measuring a concentration of a dissolved oxygen contained in a water, a water flow rate control step for controlling the supplied amount of the water, an activated carbon fiber catalyst reaction step for removing a dissolved oxygen contained in the water with the reaction between the reducing agent and the dissolved oxygen in an activated carbon fiber reactor in which an activated carbon fiber catalyst is packed, and a control step for controlling the feeding rate of the reducing agent in accordance with the water flow rate and the reactor entrance dissolved oxygen, for thereby extending the life time of the facility and decreasing the operational and maintenance costs by fully removing a dissolved oxygen in water used for an steam generator or cooling system.

Abstract: A centrifugal extractor for extraction of an organic phase from a liquid mixture, such as liquid radioactive wastes, is disclosed. In the centrifugal extractor, both the separating weir and the divert disk are designed to be adjustable in their vertical positions. The extractor, thus, desirably separates the organic phase, including usable elements in addition to chemically toxic high radioactive elements, from the aqueous phase and desirably controls the reaction time of the two phases regardless of a variation of the mixing ratio and the rotational speed of the two phases. In the centrifugal extractor, a liquid suction and rotation unit sucks and rotates the liquid mixture and separates the organic phase from the aqueous phase while controlling the reaction time of the two phases. A height-adjustable separation weir unit is designed to locate the separating weir at a boundary layer between the two separated phases.

Abstract: A high temperature superconductor bearing is disclosed which provide a strong levitation force and thus enable the construction of a horizontal-axle flywheel energy storage system. The bearing includes a magnet journal made of high temperature superconductor films, and a stator formed of a plurality of high temperature superconductors installed opposite to the high temperature superconductor magnet journal or the magnet journal for thereby off-setting the force such as the weight applied to the rotor using a magnetic pressure.

Abstract: The invention presented herein relates to a zirconium alloy with superior corrosion resistance and high strength for use in fuel rod claddings, spacer grids and structural components in reactor core of light water and heavy water nuclear power plant. The zirconium alloy of this invention with superior corrosion resistance and high strength comprises an alloy composition as follows: niobium in a range of 0.15 to 0.25 wt. %; tin in a range of 1.10 to 1.40 wt. %; iron in a range of 0.35 to 0.45; chromium in a range of 0.15 to 0.25; one element selected from the group consisting of molybdenum, copper and manganese in a range of 0.08 to 0.12 wt. %; oxygen in a range of 0.10 to 0.14 wt. %; and the balance being zirconium.