| KOREA ATOMIC ENERGY RESEARCH INSTITUTE Patent applications |
| Patent application number | Title | Published |
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| 20120135157 | Coating and Ion Beam Mixing Apparatus and Method to Enhance the Corrosion Resistance of the Materials at the Elevated Temperature Using the Same - The present invention relates to a ceramic coating and ion beam mixing apparatus for improving corrosion resistance, and a method of reforming an interface between a coating material and a base material. In samples fabricated using the coating and ion beam mixing apparatus, adhesiveness is improved, and the base material is reinforced, thereby improving resistance to thermal stress at high temperatures and high-temperature corrosion resistance of a material to be used in a sulfuric acid decomposition apparatus for producing hydrogen. | 05-31-2012 |
| 20120123721 | ELECTRONIC SCALE HAVING FUNCTION OF COMPENSATING FOR AIR PRESSURE CHANGES IN GLOVE BOX - The present invention relates to an electronic scale having an air pressure change compensation function, which can precisely measure the weight of an object to be weighed even in an environment in which air pressure changes moment by moment in an airtight space such as in a glove box. According to the present invention, there is provided an electronic scale having an internal air pressure measurement sensor, by which the function of correcting the weight of an object to be weighed is provided even in an environment in which air pressure changes such as in the glove box is provided, thus enabling the weight of a sample to be precisely measured even in an environment in which air pressure changes moment by moment. | 05-17-2012 |
| 20120106693 | HIGH Cr FERRITIC/MARTENSITIC STEELS HAVING AN IMPROVED CREEP RESISTANCE FOR IN-CORE COMPONENT MATERIALS IN NUCLEAR REACTOR, AND PREPARATION METHOD THEREOF - Disclosed herein is a high Cr Ferritic/Martensitic steel comprising 0.04 to 0.13% by weight of carbon, 0.03 to 0.07% by weight of silicon, 0.40 to 0.50% by weight of manganese, 0.40 to 0.50% by weight of nickel, 8.5 to 9.5% by weight of chromium, 0.45 to 0.55% by weight of molybdenum, 0.10 to 0.25% by weight of vanadium, 0.02 to 0.10% by weight of tantalum, 0.21 to 0.25% by weight of niobium, 1.5 to 3.0% by weight of tungsten, 0.015 to 0.025% by weight of nitrogen, 0.01 to 0.02% by weight of boron and iron balance. By regulating the contents of alloying elements such as nitrogen, born, the high Cr Ferritic/Martensitic steel with to superior tensile strength and creep resistance is provided, and can be effectively used as an in-core component material for sodium-cooled fast reactor (SFR). | 05-03-2012 |
| 20120081133 | METHOD OF DETECTING IMPURITIES IN HIGH TEMPERATURE AQUEOUS SOLUTION AND APPARATUS OF DETECTING IMPURITIES FOR THE SAME - The present invention relates to a method of detecting impurities in a high-temperature aqueous solution and an apparatus of detecting impurities for the same. Specifically, the present invention provides a method of detecting impurities in a high-temperature aqueous solution comprising a reducing agent using an electrochemical water chemistry technology detecting the electrochemical current varied according to the degree in which the impurities in the high-temperature aqueous solution hinder the formation of an oxide film that is formed on a noble metal electrode, and an impurity detecting apparatus comprising a noble metal electrode, a counter electrode, and a device of applying the electrochemical potential and measuring the electrochemical current for the method of detecting impurities. | 04-05-2012 |
| 20120063562 | DUAL-COOLED FUEL ROD'S SPACER GRIDS WITH UPPER AND LOWER CROSS-WAVY-SHAPE DIMPLE - A dual-cooled fuel rod's spacer grid with upper and lower dimples, including a blocking area of a flow passage that coolant flows through is reduced and dual-cooled fuel rods are supported, and reduces a turbulent flow of the coolant as well as vibrations of the dual-cooled fuel rods, thereby lessening fretting damage done to the rods. The spacer grid includes a plurality of unit grid straps, each of which includes a body disposed in a vertical direction, an upper dimple protruding from an upper portion of the body, and a lower dimple spaced apart from the upper dimple in a downward direction and protruding from a lower portion of the body. The unit grid straps form a grid structure that have inner grid holes into which the dual-cooled fuel rods are held, and the held dual-cooled fuel rods are each supported in four directions by the upper and lower dimples. | 03-15-2012 |
| 20120056108 | SURFACE MODIFICATION METHOD OF FLUOROPOLYMERS BY ELECTRON BEAM IRRADIATION AND THE FABRICATION OF SUPERHYDROPHOBIC SURFACES USING THE SAME - A method for the surface modification of fluoropolymer films using electron beam irradiation to generate superhydrophobic surfaces is provided. This surface modification method can cause simultaneously both a physical modification roughening the fluoropolymer surfaces and a chemical modification changing the surface composition of the fluoropolymers, and therefore fabricating the superhydrophobicity on a fluoropolymer surface by controlling the dose of electron beam irradiation. Therefore, this method for the surface modification of fluoropolymers by electron beam irradiation can be used in the generation of superhydrophobic surfaces required in various industries such as paint, glue, fine chemistry, electrical and electronics, cars, and display manufacturing. | 03-08-2012 |
| 20120043469 | RADIATION DETECTING DEVICE TO MEASURE GAMMA-RAY AND NEUTRON DISCRIMINATELY - A radiation detecting device is provided, according to which it is possible use only one radiation detecting device to measure radiation and measure gamma ray and neutron at once and discriminately in a restricted space. The radiation detecting device includes a radiation detecting unit to measure gamma ray and neutron discriminately at once, and a signal processing circuit which applies voltage to the neutron detecting unit and indicates measured gamma ray and neutron discriminately. | 02-23-2012 |
| 20120026495 | Device for On-Site Measurement of Concentration of Uranium in High Temperature Molten Salts - A device for on-site measurement of concentration of uranium in high temperature molten salts is provided. More particularly, to a device for on-site measurement of concentration of uranium in high temperature molten salts that can be directly applied to a pyroprocess for reusing spent nuclear fuel and determine concentration of uranium 3+ and 4+ chemical species using ultraviolet-visible light absorption spectrometry. The device includes first and second optical waveguides submerged in molten salts including uranium through a port formed at an upper side of a pyrochemical process apparatus; a lengthwise driver installed at the port to be operated to adjust a distance between the optical waveguides; a light source for supplying light to the second optical waveguide as any one of the optical waveguides; and a spectrometer connected to the first optical waveguide as the other one of the optical waveguides to analyze the light emitted from the second optical waveguide and introduced through the first optical waveguide via the molten salts. | 02-02-2012 |
| 20120014506 | STEREO X-RAY INSPECTION APPARATUS AND METHOD FOR FORMING THREE-DIMENSIONAL IMAGE THROUGH VOLUME RECONSTRUCTION OF IMAGE ACQUIRED FROM THE SAME - A stereo x-ray inspection apparatus and a method for forming a three-dimensional image through volume reconstruction of an image acquired from the same are disclosed. The apparatus includes one x-ray generator and two detectors to acquire two images. The x-ray generator and detectors are arranged in the form of a right-angled triangle, to easily achieve mathematical development and analysis. One of the detectors, which does not just oppose the x-ray generator, is movable and rotatable, to acquire images under the condition that only one detector is moved in accordance with the size of an object, and thus to simplify control operation for the apparatus, so that a more accurate image from an object moving at high speed is acquired. | 01-19-2012 |
| 20110299645 | Breeding Nuclear Fuel Mixture Using Metallic Thorium - Disclosed is a breeding nuclear fuel mixture including metallic thorium useable in a nuclear power plant, prepared by mixing uranium dioxide (UO | 12-08-2011 |
| 20110240817 | TELESCOPIC TUBE SET FOR BRIDGE TRANSPORT SYSTEM - A telescopic tube set for a bridge transport system is disclosed. The telescopic tube set includes cylindrical tubes each having an upper end, at which an upper ring is mounted, and a lower end, at which a lower ring is mounted, the cylindrical tubes having different diameters, pulleys mounted to respective inner wall surfaces of a part of the tubes, and extension/retraction lines each having an end connected to the upper ring of a corresponding one of the tubes, and an opposite end connected to the upper ring of another corresponding one of the tubes while extending around the pulley mounted to the tube interposed between the corresponding tubes. A plurality of bearings are installed at the lower ring to guide the tube, at which the lower ring is mounted, such that the tube extends or retracts straight in a longitudinal direction. | 10-06-2011 |
| 20110221347 | EXIT LIGHT AND EMERGENCY LIGHT WHICH HAVE FUNCTION TO INDICATE RESIDUAL CHARGE OF BATTERY - An exit light and an emergency light which have a function to indicate a residual charge of a storage battery are provided for users to efficiently check the residual charge of the battery by using a bar graph indicating unit formed on a front portion. The exit light and the emergency light each includes a power input unit which receives a utilized voltage input, decreases the voltage input and applies the voltage input to a rectifier circuit unit; the rectifier circuit which transforms AC power applied from the power input unit into DC power and applies the DC power to a power supply unit; the power supply unit which applies the DC power applied from the rectifier circuit to a light emitting unit or a charging circuit; the light emitting unit which emits light by using the DC power applied from the power supply unit; the charging circuit which supplies the DC power applied from the power supply unit to a storage battery and charges the storage battery; the storage battery which is charged with the DC power applied from the charging circuit; a bar graph indicating unit which indicates a residual charge of the storage battery; and a check switch which, in response to switching-on by a user for checking, cuts off the utilized power and discharges the charge of the storage battery through the bar graph indicating unit so that the residual charge of the storage battery is indicated on the bar graph indicating unit. | 09-15-2011 |
| 20110185790 | Leakage Detection Method and System Using Camera Image - Provided is a leakage detection system and method using an image that may detect a leakage of high temperature high pressure steam using an image. The leakage detection method may include: obtaining an image of a target where a leakage of high temperature high pressure steam occurs; detecting, in the obtained image, an edge image before the leakage occurs and an edge image after the leakage occurs; detecting only a leakage edge image by comparing the edge image before the leakage occurs and the edge image after the leakage occurs; removing noise from the leakage edge image; and displaying the leakage edge image in which the noise is removed. | 08-04-2011 |
| 20110164715 | SYSTEM AND METHOD FOR DETECTING LEAKAGE OF NUCLEAR REACTOR COOLANT USING LASER INDUCED EMISSION SPECTRUM - System and method for detecting and/or predicting in a field the leakage of nuclear reactor coolant that may occur at the pressure boundary of the primary system of a nuclear reactor. The system and method for detecting the leakage of nuclear reactor coolant uses a laser induced emission spectrum. The leakage of coolant is detected by detecting boron (B), a main component of the coolant, in corrosive products generated at the nuclear reactor pressure boundary on the basis of laser spectroscopy. An embodiment of the system for detecting leakage of nuclear reactor coolant may include a laser generator, a laser focusing lens, an emission collector, and emission spectrum analyzer. | 07-07-2011 |
| 20110162764 | HIGH-CR FERRITIC/MARTENSITIC STEEL HAVING IMPROVED CREEP RESISTANCE AND PREPARATION METHOD THEREOF - High-Cr ferritic/martensitic steels having an improved tensile strength and creep resistance are provided, which includes 0.04˜0.13 weight % of carbon, 0.03˜0.07 weight % of silicon, 0.40˜0.50 weight % of manganese, 0.40˜0.50 weight % of nickel, 8.5˜9.5 weight % of chromium, 0.45˜0.55 weight % of molybdenum, 0.10˜0.25 weight % of vanadium, 0.02˜0.10 weight % of tantalum, 0.15˜0.25 weight % of niobium, 1.5˜3.0 weight % of tungsten, 0.05˜0.12 weight % of nitrogen, 0.004˜0.008 weight % of boron, and optionally, 0.002˜0.010 weight % of phosphorus or 0.01˜0.08 weight % of zirconium, and iron balance. By regulating the contents of alloying elements such as niobium, tantalum, tungsten, nitrogen, boron, zirconium, carbon, the high-Cr ferritic/martensitic steels with superior tensile strength and creep resistance are provided, and can be effectively used as an in-core structural material for Generation IV sodium-cooled fast reactor (SFR) which is used under high temperature and high irradiation conditions. | 07-07-2011 |
| 20110144829 | COUNTERMEASURE SYSTEM FOR BIRDS - Provided is a bird countermeasure system. The bird countermeasure system includes a bird countermeasure robot configured to be operated through a remote command while patrolling or moving in an area adjacent to a runway or taxiway along which airplanes take off, land or taxi so as to approach the runway or taxiway or to detect or repel birds located close to the runway or taxiway. | 06-16-2011 |
| 20110121473 | Method for Fabricating Sintered Annular Nuclear Fuel Pellet Through Rod-Inserted Sintering - A method for fabricating a sintered annular nuclear fuel pellet includes: molding nuclear fuel powder or granules to fabricate an annular nuclear fuel green body; inserting a rod-like shaped structure into the annular nuclear fuel green body; sintering the rod-like shaped structure-inserted annular nuclear fuel green body in a reductive gas atmosphere; and separating the sintered annular nuclear fuel pellet from the rod-like shaped structure. | 05-26-2011 |
| 20110111400 | METHOD FOR ENHANCING CHEMICAL SENSITIVITY OR RADIOSENSITIVITY OF CANCER CELLS BY INHIBITING EXPRESSION OF TSPYL5 - Disclosed herein is a method for enhancing sensitivity of cancer cells to compounds or radiation by inhibiting the expression of testis-specific protein, Y-encoded like 5 (TSPYL5). More specifically, because methylation of TSPYL5 protein expressed in lung cancer cell line was inhibited to increase the expression level of the gene, resistance to stress such as radiation or anticancer agents was increased. Because the sensitivity of cancer cells to stress such as radiation or anticancer agents was increased by inhibiting the expression of the TSPYL5 gene to promote the apoptosis of the cells, an anticancer supplement agent containing an inhibitor of the expression or activity of the TSPYL5 gene of the present invention inhibits the growth of cancer cells and enhances the sensitivity to various stresses to maximize the apoptosis. Thus, when used in combination with radiotherapy or chemotherapy, the anticancer supplement agent may be used very usefully for anticancer treatment. | 05-12-2011 |
| 20110098995 | METHOD FOR DESIGNING CONCENTRIC AXIS DOUBLE HOT GAS DUCT FOR VERY HIGH TEMPERATURE REACTOR - Provided is a method of designing a coaxial dual-tube type hot gas duct for a very-high-temperature reactor. When determining the outer diameter of an inner tube and the inner diameter of a pressure tube, both of which defines an annular part of the hot gas duct having a dual-tube shape, one selected from hydraulic heads, flow rates, and hydraulic heads of very-high-temperature helium gas flowing to a very-high-temperature region and low-temperature helium gas flowing to a low-temperature region is taken into consideration as well as is a relation of about heat balance model, so that it is possible to minimize flow induced vibrations caused by the flow of a fluid. | 04-28-2011 |
| 20110091001 | HIGH CURRENT SOLID TARGET FOR RADIOISOTOPE PRODUCTION AT CYCLOTRON USING METAL FOAM - Disclosed herein is a high current solid target for radioisotope production at a cyclotron using a metal foam, and more specifically, a high current solid target for isotope production, which attaches a metal foam to the rear surface of the solid target plate. A high current solid target for isotope production including a metal foam according to the present invention may exhibit excellent cooling performances to increase the amount of proton beam current irradiated on the solid target compared to conventional planar-type solid targets. Because the irradiation of the increased proton beam current may increase the amount of an isotope produced per unit time and even an irradiation of proton beam in a short time may allow for production of a desired amount of an isotope, the solid target may be usefully used for production of medical cyclotron nuclides. | 04-21-2011 |
| 20110064184 | UNIT SPACER GRID STRAP, UNIT SPACER GRID, AND SPACER GRID FOR NUCLEAR FUEL RODS - A spacer grid for nuclear fuel rods includes a plurality of unit spacer grids stacked one on top of another. Each unit spacer grid includes a plurality of unit spacer grid straps disposed at regular intervals in a row, and a plurality of fixing grid straps connected to respective opposite ends of the unit spacer grid straps so as to fix the unit spacer grid straps. Each unit spacer grid strap has convexities alternating with each other on opposite sides thereof at regular intervals, and at least one of the convexities has a diameter greater than the others. The unit spacer grids are rotated in one direction by a 90 or 180 degree angle when being stacked. | 03-17-2011 |
| 20110056647 | INGOT-CASTING APPARATUS USING URANIUM DEPOSITS - A casting apparatus includes a hermetically sealed chamber, wherein the chamber includes: a melt-heating portion to melt external uranium deposits, the melt-heating portion being tiltable to allow the resulting liquid molten material to be discharged to the outside, an ingot-forming portion to receive the molten material discharged from the melt-heating portion and to cool-solidify the molten material, and a salt-capturing portion provided on the melt-heating portion, to solidify a salt gas produced when the uranium deposits are molten, and thereby recover the salt gas, wherein the ingot-forming portion includes: a horizontal turn-table rotated by an operating means, and a plurality of molds mounted on the edge of the turn-table, each containing the molten material, which is then cooled. | 03-10-2011 |
| 20110052461 | FILTER TYPE TRAPPING AGENT FOR VOLATILE CESIUM COMPOUND AND TRAPPING METHOD FOR VOLATILE CESIUM COMPOUND THEREOF - A filter type trapping agent for volatile cesium compound and trapping method for volatile cesium compound thereof are provided. More particularly, a filter type trapping agent for volatile cesium compound including silica 40˜65% by weight of silica, 15˜30% by weight of alumina, 5˜15% by weight of iron oxide, 1˜15% by weight of molybdenum oxide, 1˜10% by weight of chromium oxide, and 1˜10% by weight of vanadium oxide and trapping method for volatile cesium compound thereof are provided. Through a filter type trapping agent for volatile cesium compound and a trapping method, only cesium can be selectively separated among the nuclear fission gases. Accordingly, by disposing only the filter where cesium is trapped, the efficiency of an off-gas process improves, expense for disposing filter wastes decreases, and a cesium isotope of the waste filter can be recycled. Therefore, many forms of cesium compound gas are made insoluble efficiently. | 03-03-2011 |
| 20110051882 | TRUSS-REINFORCED SPACER GRID AND METHOD OF MANUFACTURING THE SAME - A truss-reinforced spacer grid and a method of manufacturing the same are provided, in which truss members having a small diameter are woven to form a truss structure surrounded by an external plate, and the truss structure is joined to the external plate to thereby improve the strength of the mechanical structure. The truss-reinforced spacer grid includes a truss structure in which horizontal trusses formed by horizontally weaving a plurality of truss members are vertically disposed at regular intervals, and an external plate is joined with ends of the horizontal trusses and surrounds the truss structure. | 03-03-2011 |
| 20110050890 | METHOD AND SYSTEM FOR MEASURING STRUCTURAL VIBRATION USING CURVE FITTING FROM VIDEO SIGNAL - A method and system for measuring structural vibration using curve fitting from a video signal, which can reduce an error in vibration measurement displacement, is provided. A method for measuring structural vibration using curve fitting from a video signal, the method includes the steps of: obtaining a video signal of the object; converting the video signal of the object into a gray video signal; adjusting the brightness of the converted video signal; separating an area to be measured from the brightness-adjusted video signal; selecting an edge area of the object from a video signal of the separated area; removing noises from the edge regions; and performing curve fitting with respect to the noise-removed video signal of the edge area. Accordingly, a displacement error is reduced, so that vibration can be more exactly measured. | 03-03-2011 |
| 20110049734 | Method for Preparing Sintered Annular Nuclear Fuel Pellet - A method for fabricating a sintered annular nuclear fuel pellet includes molding nuclear fuel powder or granule, an oxide of a fissile element (M), to fabricate an annular nuclear fuel green body. A rod-like shaped structure is inserted into the annular nuclear fuel green body and sintered in a slight oxidizing gas atmosphere such that the oxide of the fissile element has a balanced O/M ratio higher than a desired O/M ratio (oxygen/fissile element) of a final sintered annular nuclear fuel pellet, while being maintained in a cubic phase. The sintered annular nuclear fuel pellet is then reduced in a reductive gas atmosphere so as to have the desired O/M ratio in the state that the rod-like shaped structure is inserted. | 03-03-2011 |
| 20110031450 | CONDUCTIVE NANOCOMPLEX AND METHOD OF MANUFACTURING THE SAME - Provided is a nanocomplex comprising a core consisting of a metal; and a periphery being formed on a surface of the core to surround the core and consisting of an inorganic substance and a conductive polymer | 02-10-2011 |
| 20110020206 | ADSORBENT, PREPARATION METHOD THEREOF AND SR-90/Y-90 GENERATOR USING THE SAME - Disclosed herein is an radioisotope adsorbent including a bifunctional organosilane compound, including an organosiloxane functional group and a phosphate group, bonded on the surface of silica which is a bone structure of the adsorbent, and a method of preparing the radioisotope adsorbent, and a strontium/yttrium generator using the radioisotope adsorbent. Since the radioisotope adsorbent has a high adsorption capacity for | 01-27-2011 |
| 20110017601 | Method for Recovery of Residual Actinide Elements from Chloride Molten Salt - A method for recovery of residual actinide element from chloride molten salts that are formed after electro-refining and/or electro-winning of a spent nuclear fuel and include actinide elements and rare-earth elements is provided. The method comprises conducting electrolysis using a liquid cadmium cathode (LCC) in the chloride molten salt that is formed after electro-refining and/or electro-winning of a spent nuclear fuel and contains rare-earth elements and actinide elements; electro-depositing the actinide elements contained in the chloride molten salt on the LCC in order to reduce a concentration of the actinide elements; and adding a CdCl | 01-27-2011 |
| 20100322370 | PROCESS OF MANUFACTURING ZIRCONIUM ALLOY FOR FUEL GUIDE TUBE AND MEASURING TUBE HAVING HIGH STRENGTH AND EXCELLENT CORROSION RESISTANCE - A process of manufacturing zirconium alloy. The process may be used to make a nuclear fuel guide tube and/or a measuring tube which are main components of a nuclear fuel assembly structure. While a nuclear fuel guide tube and a measuring tube are manufactured by performing three-step cold working, and intermediate and final thermal annealing from a semi-finished TREX shell in the conventional method, the present invention relates to zirconium alloy undergoing two-step cold working, and intermediate and final thermal annealing from a TREX shell, resulting in enhanced strength and corrosion resistance. The present invention may be applied to a nuclear fuel guide tube and a measuring tube used for a nuclear fuel assembly in a light water nuclear reactor because, by the shortened process, high percentage reduction in thickness between processes and an decrease in thermal annealing time may sustain high strength and excellent corrosion resistance, and achieve economy of manufacture by reducing the number of processes. | 12-23-2010 |
| 20100317911 | METHOD FOR PREPARING CERAMIC WASTE FORM CONTAINING RADIOACTIVE RARE-EARTH AND TRANSURANIC OXIDE, AND CERAMIC WASTE FORM WITH ENHANCED DENSITY, HEAT-STABILITY, AND LEACH RESISTANCE PREPARED BY THE SAME - Disclosed herein is a method for preparing a ceramic waste form containing radioactive rare-earth and transuranic oxide, and the ceramic waste form with enhanced density, heat-stability, and leach resistance prepared by the same. | 12-16-2010 |
| 20100301851 | APPARATUS AND METHOD FOR SEARCHING EDDY CURRENT OF ELECTRIC HEAT TUBE USING MEASURING MAGNETIC PERMEABILITY IN STEAM GENERATOR - A detection apparatus for an eddy current in a heat generating tube using a permeability measurement method, and a method using the apparatus are provided. In the detection apparatus, a bobbin type probe acquires detection information with respect to a magnetic flux change by a magnetic phase occurring in the heat generating tube using a coil which is wound in an axis direction of at least one yoke located in a perpendicular direction with a bobbin of the bobbin type probe, and a material having a corresponding magnetic phase and a circumferential defect, which is difficult to be detected by the bobbin type probe, are detected based on the detection information. | 12-02-2010 |
| 20100292166 | PHARMACEUTICAL COMPOSITION FOR TREATING MALIGNANT TUMORS CONTAINING HUMAN p31 GENES - A pharmaceutical composition for the treatment of malignant tumors comprising a human p31 | 11-18-2010 |
| 20100278294 | EMERGENCY CORE COOLING DUCT FOR EMERGENCY CORE COOLING WATER INJECTION OF A NUCLEAR REACTOR - The present invention relates to a longitudinally divided emergency core cooling (ECC) duct in order to efficiently inject safety water to core of a pressurized light-water nuclear reactor. The ECC duct includes side supports for preventing the flow-induced vibration in the annular downcomer, and has structural stability while thermally expanding and contracting. A longitudinally divided ECC duct for emergency core cooling water injection of a nuclear reactor is provided on the periphery of a core barrel of a nuclear reactor, includes an emergency core cooling water inlet facing a direct vessel injection nozzle, and extends in a longitudinal direction of the core barrel. The longitudinally divided ECC duct is divided into a plurality of longitudinally-divided ducts in the longitudinal direction of the longitudinally divided ECC duct. | 11-04-2010 |
| 20100272616 | SYSTEM AND APPARATUS OF SEPARATING REMAINING POWER OF HULL - An apparatus and system for separating remaining powder of hulls includes a first remaining powder separating unit to be supplied with hulls of a spent nuclear fuel subjected to a high-temperature oxidation, and to include a first brush for separating remaining powder of the hulls; a hull alignment unit to be supplied with the hulls from the first remaining powder separating unit, and to align the hulls; a second remaining powder separating unit to be supplied with the aligned hulls from the hull alignment unit, and to include a second brush for separating remaining powder adhered on an inner peripheral surface of the hulls; and a third remaining powder separating unit to be supplied with the hulls from the second remaining powder separating unit, and to separate the remaining powder remaining on the inner/outer peripheral surface of the hulls by using air. | 10-28-2010 |
| 20100254847 | METHOD FOR MANUFACTURING SINTERED ANNULAR NUCLEAR FUEL PELLET WITHOUT SURFACE GRINDING - A method for manufacturing an annular nuclear fuel pellet is provided. In the method, an annular nuclear fuel green compact whose lateral cross-section is a trapezoid is prepared. The thickness of the annular nuclear fuel green compact reduces along one direction of the central axis, and a green density of the nuclear fuel green compact increases along one direction of the central axis. The annular nuclear fuel green compact is sintered under a reducing gas atmosphere so that the annular nuclear fuel pellet is obtained. According to this method, the annular pellet which has uniform inner and outer diameters and small diametric tolerances along the pellet height is fabricated without grinding the pellet surfaces. | 10-07-2010 |
| 20100248955 | Adsorbents for Radioisotopes, Preparation Method Thereof, and Radioisotope Generators Using the Same - Disclosed is a novel adsorbent for use in a | 09-30-2010 |
| 20100239062 | COOLANT WITH DISPERSED NEUTRON POISON MICRO-PARTICLES, USED IN SCWR EMERGENCY CORE COOLING SYSTEM - Disclosed is a coolant with dispersed neutron poison micro-particles, used in a supercritical water-cooled reactor (SCWR) emergency core cooling system. Since the neutron poison micro-particles are uniformly dispersed in the coolant of the emergency core cooling system for a long period time, their fluidity is not lowered even though the polarity of water is changed in a supercritical state. Therefore, the neutron poison micro-particles absorb neutrons produced from nuclear fission in a nuclear reactor core. Accordingly, the neutron poison micro-particles can be appropriately used as a means for controlling neutrons and stopping a nuclear reactor in the SCWR emergency core cooling system. | 09-23-2010 |
| 20100177860 | FULLY PASSIVE DECAY HEAT REMOVAL SYSTEM FOR SODIUM-COOLED FAST REACTORS THAT UTILIZES PARTIALLY IMMERSED DECAY HEAT EXCHANGER - Disclosed herein is a fully passive decay heat removal system utilizing a partially immersed heat exchanger, the system comprising: a hot pool; an intermediate heat exchanger which heat-exchanges with the sodium of the hot pool; a cold pool; a support barrel extending vertically through the boundary between the hot pool and the cold pool; a sodium-sodium decay heat exchanger received in the support barrel; a sodium-air heat exchanger provided at a position higher than the sodium-sodium decay heat exchanger; an intermediate sodium loop connecting the sodium-sodium decay heat exchanger with the sodium-air heat exchanger; and a primary pump, wherein a portion of the effective heat transfer tube of the sodium-sodium decay heat exchanger is immersed in the cold pool, particularly in a normal operating state, and the surface of the lower end of a shroud for the sodium-sodium decay heat exchanger, the lower end being immersed in the sodium of the cold pool, has perforated holes. | 07-15-2010 |
| 20100172460 | PERFORATED PLATE SUPPORT FOR DUAL-COOLED SEGMENTED FUEL ROD - A perforated plate support supports dual-cooled fuel rods, each of which has concentric outer and inner tubes and is coupled with upper and lower end plugs at upper and lower ends thereof, and guide thimbles, each of which is used as a passage for a control rod. The perforated plate support is formed as a support plate having the shape of a flat plate, which includes internal channel holes, each of which has a diameter corresponding to an outer diameter of the inner tube, guide thimble holes, each of which has a diameter corresponding to an outer diameter of the guide thimble, and sub-channel holes around each internal channel hole. The upper or lower end of the dual-cooled fuel rod is coupled to the support plate such that the outer diameter of the inner tube is matched with the diameter of the internal channel hole. | 07-08-2010 |
| 20100163746 | Irradiation device for material test using gamma ray from spent nuclear fuel assembly - The present invention relates to an irradiation device for material test using a gamma ray radiated from a spent nuclear fuel assembly and provides the irradiation device for material test using a gamma ray radiated from a spent nuclear fuel assembly wherein an irradiation device for material test to achieve a radiation effect evaluation is manufactured to be movable upward, downward and horizontally in order to study the hardening phenomenon of the frail materials to the radiation among the atomic power facilities using a gamma ray radiated from a spent nuclear fuel assembly, thereby it is possible to adjust a position of the spent nuclear fuel used for material test using a gamma ray radiated from a spent nuclear fuel and a test material, identify a distance between the spent nuclear fuel and the test material easily with a scale and evaluate the radiation effects on the materials used at facilities handling a spent nuclear fuel under the same situation as they are really exposed. Further the present invention comprises a support constructed vertically; a vertical moving table which is capable of moving upward and downward connected with a proper position of the support; a moving device for moving said vertical moving table upward and downward; a horizontal moving table which is capable of moving horizontally placed on the vertical moving table; a horizontal moving bar which is capable of moving horizontally placed on the vertical moving table; and a driving device for driving the horizontal moving table and the horizontal moving bar horizontally. | 07-01-2010 |
| 20100155236 | Corrosion Resistant Structural Alloy for Electrolytic Reduction Equipment for Spent Nuclear Fuel - Disclosed is a structural alloy with oxidation resistance for electrolytic reduction equipment for treatment of spent nuclear fuel. More particularly, the present invention relates to a structural alloy with oxidation resistance for electrolytic reduction equipment for treatment of spent nuclear fuel wherein Cr, Si, Al, Nb and Ti are added to a Ni-based substrate so as to form an oxide coating film which is stable in a LiCl—Li | 06-24-2010 |
| 20100142668 | POROUS PLENUM SPACER FOR DUAL-COOLED FUEL ROD - A porous plenum spacer is inserted into the plenum of a dual-cooled fuel rod having concentric inner and outer cladding tubes. The porous plenum spacer includes a hollow cylindrical body inserted into the annular space between the inner and outer cladding tubes. The hollow cylindrical body includes a plurality of through-holes formed in an outer circumference thereof or at least one groove formed in one of outer and inner circumferences thereof in a lengthwise direction. Pores formed by the through-holes or the grooves of the hollow cylindrical body of the porous plenum spacer are allowed to secure a space containing fission gas inevitably generated by a nuclear reaction. | 06-10-2010 |
| 20100140522 | Separable Ball Valve Apparatus and Ball Valve Assembly - A separable ball valve apparatus and ball valve assembly capable of selectively opening/closing a separable flow path are provided. The separable ball valve apparatus comprises a separable pipe member having a flow path through which fluid flows, a ball member having at least two balls disposed in the pipe member, opening and closing the flow path, and adjacent to each other, and an opening/closing member configured to control the ball member to open/close the flow path, wherein the balls have through-holes, respectively, and the opening/closing member includes a gear train configured to control the opening/closing of the at least two balls. Therefore, it is possible to simply open/close pipes having the flow path and detachably attach the pipes, increase space utilization due to removal of a separate coupling space for attachment/detachment of the pipes, and simultaneously open/close the two pipes, which are separated from each other through one operation. | 06-10-2010 |
| 20100135452 | LIQUID-METAL-COOLED FAST REACTOR CORE COMPRISING NUCLEAR FUEL ASSEMBLY WITH NUCLEAR FUEL RODS WITH VARYING FUEL CLADDING THICKNESS IN EACH OF THE REACTOR CORE REGIONS - A liquid-metal cooled fast reactor core having a nuclear fuel assembly constituted of nuclear fuel rods with varying cladding thicknesses in reactor core regions, in which: the nuclear fuel assembly ( | 06-03-2010 |
| 20100128835 | INTERMEDIATE END PLUG ASSEMBLY FOR SEGMENTED FUEL ROD AND SEGMENTED FUEL ROD HAVING THE SAME - An intermediate end plug assembly for a segmented fuel rod can stably support the fuel rod to the end of its cycle even if an interval between the fuel rods becomes narrow due to application of a dual-cooled fuel rod, and reduce excess vibration induced by flows of interior and exterior channels of the dual-cooled fuel rod for obtaining high burnup and output. To this end, the fuel rod has a segmented structure so as to make its length short. A lower intermediate end plug includes at least one channel hole, through which a coolant flows into an internal channel of the fuel rod, so that a possibility of causing departure from nuclear boiling ratio (DNBR) of the dual-cooled fuel rod is reduced. | 05-27-2010 |
| 20100126713 | Fluid Collecting Apparatus - A fluid collecting apparatus inserted in a borehole for collecting fluid in the borehole. The fluid collecting apparatus may include a first packer and a second packer which are selectively adhered to an inside of the borehole, a first supply pipe and a second supply pipe which supply expansion fluid to each of the first packer and the second packer, and a guide tube which guides fluid in a collecting space between the first packer and the second packer to an outside of the borehole. Also, the second supply pipe moves with the second packer in a longitudinal direction of the borehole, and a passage which does not communicate with the first supply pipe is formed. Accordingly, the fluid collecting apparatus may independently control the first and second packers, and thus fluid in a desired depth and region within the borehole may be easily collected. | 05-27-2010 |
| 20100124669 | JOINING METHOD BETWEEN Fe-BASED STEELS AND Ti/Ti-BASED ALLOYS HAVING JOINT STRENGTH HIGHER THAN THOSE OF BASE METALS BY USING INTERLAYERS AND THE JOINTS PRODUCED USING THE METHOD - A joining method between Fe-based steel and Ti/Ti-based alloys having a joint strength higher than those of base metals by using interlayers. The production of intermetallic compounds at a joint portion between Fe-based steel and Ti/Ti-based alloys can be prevented using interlayers, and strong interface diffusion bonding can be formed at interfaces between interlayers, thereby producing a high-strength joint. Accordingly, the present disclosure can be used to develop high-strength, high-functional advanced composite materials. | 05-20-2010 |
| 20100118294 | Apparatus for Detecting the Leakage of Heavy Water in Nuclear Reactor System and Detection Method Using the Same - An apparatus and a method for detecting a leakage of heavy water in a nuclear reactor system includes: a diode laser that generates a laser beam and injects the generated laser beam to a test sample placed in a light absorption cell; the light absorption cell accommodates a gathered test sample therein; a vacuum pump adjusts a degree of vacuum in the light absorption cell; a test sample introduction unit gathers an air test sample from a location with a high possibility of a leakage of heavy water or a light water test sample from a secondary side of a steam generator and transfers the sample to the light absorption cell; an optical detector detects the laser beam which has passed through the light absorption cell; and a microprocessor controls the operation of the diode laser, the light absorption cell, the vacuum pump, the test sample introduction unit, and the optical detector, receives a detect signal from the optical detector, and analyzes an absorption spectrum signal. | 05-13-2010 |
| 20100108204 | ZIRCONIUM ALLOY COMPOSITION FOR NUCLEAR FUEL CLADDING TUBE FORMING PROTECTIVE OXIDE FILM, ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING TUBE MANUFACTURED USING THE COMPOSITION, AND METHOD OF MANUFACTURING THE ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING TUBE - Disclosed herein is a zirconium alloy composition for nuclear fuel cladding tubes, comprising: 1.6˜2.0 wt % of Nb; 0.05˜0.14 wt % of Sn; 0.02˜0.2 wt % of one or more elements selected from the group consisting of Fe, Cr and Cu; 0.09˜0.15 wt % of O; 0.008˜0.012 wt % of Si; and a balance of Zr, a nuclear fuel cladding tube comprising the zirconium alloy composition, and a method of manufacturing the nuclear fuel cladding tube. Since the nuclear fuel cladding tube made of the zirconium alloy composition can maintain excellent corrosion resistance by forming a protective oxide film thereon under the conditions of high-temperature and high-pressure cooling water and water vapor, it can be usefully used as a nuclear fuel cladding tube for light water reactors or heavy water reactors, thus improving the economical efficiency and safety of the use of nuclear fuel. | 05-06-2010 |
| 20100102279 | RADIATION SHIELDING MEMBERS INCLUDING NANO-PARTICLES AS A RADIATION SHIELDING MATERIAL AND METHOD FOR PREPARING THE SAME - Disclosed is a radiation shielding member having improved radiation absorption performance, including 80.0˜99.0 wt % of a polymer matrix or metal matrix and 1.0˜20.0 wt % of a radiation shielding material in the form of nano-particles having a size of 10˜900 nm as a result of pulverization, wherein the radiation shielding material is homogeneously dispersed in the matrix through powder mixing or melt mixing after treatment with a surfactant which is the same material as the matrix or which has high affinity for the matrix. A preparation method thereof is also provided. This radiation shielding member including the nano-particles as the shielding material further increases the collision probability of the shielding material with radiation, compared to conventional shielding members including micro-particles, thus reducing the mean free path of radiation in the shielding member, thereby exhibiting superior radiation shielding effects. At the same density, the shielding member has reduced thickness and volume and is thus lightweight. The porosity of the shielding member is minimized, thereby preventing the deterioration of shielding effects and properties of the shielding member and realizing applicability in spent fuel managing transport/storage environments and the like. | 04-29-2010 |
| 20100092437 | RADIATION INDUCIBLE PROMOTER - The present invention relates to a radiation inducible promoter, more particularly to a radiation inducible promoter including a base sequence represented by SEQ ID NO: 3 derived from | 04-15-2010 |
| 20100091933 | METHOD OF PRODUCING LARGE-GRAINED NUCLEAR FUEL PELLET BY CONTROLLING CHROME CATION SOLUBILITY IN UO2 LATTICE - In a method of producing large-grained nuclear fuel pellet, Cr-compound contained in an uranium oxide green pellet is reduced to Cr phase at 1,470° C. or below and maintained to the Cr phase, and the uranium oxide green pellet containing the Cr-compound is then sintered at 1,650° C.-1,800° C. in a gas atmosphere of oxygen potential at which Cr element in the uranium oxide green pellet becomes liquid phase. | 04-15-2010 |
| 20100088059 | ABNORMAL SIMULATION SIGNAL ANALYSIS METHODS AND ABNORMAL SIGNAL SIMULATION ANALYSIS MODULE FOR 4.about.20mA INSTRUMENTAL SYSTEM - The present invention relates to a negative pulse transient signal analysis methods and negative pulse transient signal analysis module for a PC base simulation equivalent circuit capable of grasping and improving error causes through an abnormal signal analysis after configuring a simulation equivalent circuit for a 4˜20 mA instrument unsatisfied in a temperature environmental impact assessment. | 04-08-2010 |
| 20100084265 | CONTINUOUS ELECTROREFINING DEVICE FOR RECOVERING METAL URANIUM - Disclosed is a continuous electrorefining device for recovering metal uranium. The electrorefining device comprises an electrolytic cell | 04-08-2010 |
| 20100071408 | METHOD OF RECYCLING LiCl SALT WASTES BY USING LAYER CRYSTALLIZATION AND APPARATUS FOR THE SAME - Disclosed herein are a method of recycling LiCl salt wastes comprising radionuclides and an apparatus using the same. The method includes a) solidifying a LiCl salt contained in the LiCl salt wastes and contacting the outer wall of a housing, by charging a crystallizer comprising the housing having an internal accommodating space and an air cooler in the internal accommodating space into a crystallizing furnace accommodating the LiCl salt wastes comprising the radionuclides, and by cooling the housing to a temperature of two-phase region where the liquid state and the solid state of the LiCl salt waste coexist, b) separating the crystallizer where the LiCl salt is solidified from the crystallizing furnace, c) recycling the LiCl salt by heating the separated crystallizer to melt the solidified LiCl salt. | 03-25-2010 |
| 20100051607 | High-Frequency Inductive Heating Apparatus and Pressure-Less Sintering Method Using the Same - A high-frequency inductive heating apparatus of ceramic material, whereby the nonconductive ceramic specimen in which induced current is not generated at room temperature is rapidly heated in a preheating housing, and a pressure-less sintering method using the same, are disclosed. The high-frequency inductive heating apparatus includes a preheating housing placed in a chamber to preheat a ceramic material; an induction coil installed around the preheating housing for supplying induced current so that the preheating housing is heated; and a high-frequency current generator for supplying high-frequency current to the induction coil. According to the present invention, inductive heating is made possible of nonconductive ceramic material for which inductive heating has thus far been impossible because induced current is not generated at room temperature, so that rapid heating by the self-heating of the specimen of ceramic material is possible. | 03-04-2010 |
| 20100051246 | HIGH TEMPERATURE AND HIGH PRESSURE CORROSION RESISTANT PROCESS HEAT EXCHANGER FOR A NUCLEAR HYDROGEN PRODUCTION SYSTEM - A high-temperature and high-pressure corrosion-resistant process heat exchanger for a nuclear hydrogen production system decomposes sulfite (SO | 03-04-2010 |
| 20100032288 | COATING AND ION BEAM MIXING APPARATUS AND METHOD TO ENHANCE THE CORROSION RESISTANCE OF THE MATERIALS AT THE ELEVATED TEMPERATURE USING THE SAME - The present invention relates, in general, to shoes for measuring the quantity of motion and a method of measuring the quantity of motion using the shoes and, more particularly, to artificial intelligence shoes, in which various numerical values (calorie consumption, body fat, and a pulse), measured by a walking sensor ( | 02-11-2010 |
| 20100029507 | THE BIOCHIP FOR THE DETECTION OF PHOSPHORYLATION AND THE DETECTION METHOD USING THE SAME - The present invention relates to a biochip for the detection of phosphorylation and a method for measuring phosphorylation using the same, more precisely a biochip integrated with the substrate of kinase and a kit for measuring phosphorylation comprising the biochip and a radio-labeled co-factor, and a method for measuring phosphorylation using the same. The kit for the detection of phosphorylation of the present invention facilitates simple and fast measurement of phosphorylation with a minimum amount of a sample, compared with the conventional method using an antibody, because it uses a radioisotope. This chip and kit can be effectively used for the analysis of kinase activity since this method favors fast mass analysis. | 02-04-2010 |
| 20100027734 | SPACER GRID FOR DUAL-COOLING NUCLEAR FUEL RODS USING INTERSECTIONAL SUPPORT STRUCTURES - A spacer grid for dual-cooling nuclear fuel rods arranged at a narrow interval. The spacer grid solves the problem in which, since the dual-cooling nuclear fuel rods are used to improve the cooling performance and stability of nuclear fuel and obtain high burnup and output, the outer diameter of each dual-cooling nuclear fuel rod is increased, and thus the gap between each dual-cooling nuclear fuel rod and the grid strap is decreased. The spacer grid includes first grid straps and second grid straps, which are crossed and arranged in transverse and longitudinal directions at regular intervals and have the shape of a flat strip, and support structures, which are fitted into the first and second grid straps around intersections of the first and second grid straps so as to support the dual-cooling nuclear fuel rods. | 02-04-2010 |
| 20090317849 | BIOCHIP FOR THE DETECTION OF PHOSPHORYLATION AND THE DETECTION METHOD USING THE SAME - The present invention relates to a biochip for the detection of phosphorylation and a detection method of phosphorylation using the same, more precisely a biochip prepared by integrating a recombinant fusion protein produced from the reaction of a kinase matrix selected from the group consisting of PKC (Protein Kinase C), cc2-PK (cdc2 Protein Kinase) and DNA-PK (DNA-dependent Protein Kinase) and the elevated protein Selenomonas ruminantium membrane protein on a substrate coated with an active group, a detection kit of phosphorylation composed of the said biochip and a cofactor labeled with a radio-isotope and a detection method of phosphorylation using the same. The biochip for the detection of phosphorylation of the present invention using a radio-isotope facilitates the detection of phosphorylation with a minimum amount of a sample by simple processes, compared with the conventional method using an antibody. Since this method can analyze a large amount of samples in a shorter period of time, it can be effectively used for the analysis of kinase activity. | 12-24-2009 |
| 20090294113 | Heat exchanger - Disclosed is a heat exchanger. The heat exchanger includes a plurality of plates superimposed on one another, and a plurality of heat transfer fins formed on the plurality of plates, and shaped into an airfoil, wherein a channel of a fluid between the superimposed plates is formed to perform a heat exchange. | 12-03-2009 |
| 20090288949 | REFERENCE ELECTRODE INCLUDING ELECTROLYTE CONTAINING OPTICALLY-ACTIVE MATERIAL AND AUTOMATIC ELECTROCHEMICAL POTENTIAL CORRECTION APPARATUS USING THE SAME - Disclosed herein is a reference electrode including an electrolyte containing an optically-active material, including: an electrode body provided at an end thereof with an electrolyte separation membrane and charged therein with an optically-active material and an electrolyte solution; an inner electrode disposed in the electrode body to be immersed in the electrolyte solution; and an absorbance measurement probe for transmitting light to the electrolyte solution and collecting reflected light waves, which is disposed in the electrode body to be immersed in the electrolyte solution. Since the concentration of an electrode reaction material, such as Cl | 11-26-2009 |
| 20090286959 | High Molecular Weight Fibroin Having Improved Antioxidant Activity, Tyrosinase Inhibitory Ability and/or Cytotoxicity to Cancer Cells by Irradiation, and Methods of Making and Using the Same - Disclosed are a fibroin with increased molecular weight and improved antioxidant activity, tyrosinase inhibitory ability and cytotoxicity to cancer cells, which has a molecular structure modified by irradiation, a method for production thereof, use of the irradiated fibroin in various applications for enhancing antioxidant activity, tyrosinase inhibitory ability and/or cytotoxicity to cancer cells such as foods, cosmetics, medicines, etc. | 11-19-2009 |
| 20090277828 | Adsorbents for Radioisotopes, Preparation Method Thereof, and Radioisotope Generators Using the Same - Disclosed is a novel adsorbent for use in a | 11-12-2009 |
| 20090274259 | RADIOISOTOPE PRODUCTION GAS TARGET HAVING FIN STRUCTURE - A radioisotope production gas target for producing gas isotopes such as C-11. The radioisotope production gas target includes a target chamber that is in the shape of a hollow cylinder and has a plurality of inner fins protruding from an inner surface thereof along a length thereof, and a body that is shaped of a hollow cylinder enclosing the target chamber, and has a target gas inlet for feeding target gas to a hollow region of the target chamber, a target gas outlet for collecting the target gas after a nuclear reaction occurs, and a first coolant inlet and a first coolant outlet respectively feeding and discharging a coolant flowing along an outer surface of the target chamber, and includes a thin metal sheet in front thereof through which a beam of protons passes. | 11-05-2009 |
| 20090269261 | Process for Recovering Isolated Uranium From Spent Nuclear Fuel Using a Highly Alkaline Carbonate Solution - Disclosed is a process for recovery of uranium from a spent nuclear fuel using a carbonate solution, characterized by excellent proliferation resistance of preventing leaching of transuranium element (TRU) nuclides such as Pu, Np, Am, Cm, etc. from the spent nuclear fuel as well as environmental friendliness of minimizing waste generation, wherein a highly alkaline carbonate solution is used to separate uranium alone from the spent nuclear fuel. | 10-29-2009 |
| 20090263906 | METHOD OF ANTIOXIDATIVE FUNCTIONAL ESTIMATION USING ANIMAL MODEL - The present invention relates to a method of antioxidative functional estimation using an animal model, more precisely a method of antioxidative functional estimation using mice having oxidative damage caused by reactive oxygen species induced by irradiation and having lipid hydroperoxide secreted in the urine which might be index for quantitative and qualitative analysis for antioxidative functional estimation. The method of antioxidative functional estimation of the present invention can be effectively used for the screening of a novel anti-oxidant agent or antioxidative functional health food to regulate the production of lipid hydroperoxide. | 10-22-2009 |
| 20090260971 | METHOD OF PREPARING FLUOROALKYL COMPOUNDS USING RADIATION - Disclosed herein is a method of preparing a fluoroalkyl compound using radiation, including: mixing an alkyl compound having a leaving group with tetrabutylammonium fluoride (TBAF) in the presence of a reaction solvent at room temperature to form a mixed solution (step 1); and applying radiation to the mixed solution while stirring it to prepare a fluoroalkyl compound (step 2). The method of preparing a fluoroalkyl compound using radiation is advantageous in that fluoroalkyl compounds can be easily prepared in a short reaction time at room temperature, in that the method is safe because it is not required to use fluorine gas, which is harmful to the human body, in that the method can be usefully used to prepare fluoroalkyl compounds because the yield of fluoroalkyl compounds obtained using the method is higher than when using conventional SN2 reaction methods, and in that fluorine | 10-22-2009 |
| 20090252883 | METHOD OF PREVENTING CORROSION DEGRADATION USING NI OR NI-ALLOY PLATING - Disclosed herein is a method of preventing corrosion degradation in a defective region including an expansion transition region and/or an expansion region of a heat transfer tube of a steam generator in a nuclear power plant by using nickel (Ni) plating or nickel (Ni) alloy plating. The method can prevent various types of corrosion damage, such as pitting corrosion, abrasion, stress corrosion cracking, lead-induced stress corrosion cracking and the like, occurring during the operation of the steam generator, and particularly, pitting corrosion or primary and secondary stress corrosion cracking, so that the life span of the steam generator is increased, maintenance costs are reduced, and the operation rate of a nuclear power plant is increased, with the result that the unit cost of the production of electric power can be decreased, thereby improving economic efficiency. Further, the method can be usefully used to prevent the corrosion damage of parts and equipment of nuclear, hydroelectric or thermoelectric power plants or of petrochemical plants, and that of industrial and machine parts and equipment, and parts and equipment in a defense industry. | 10-08-2009 |
| 20090246128 | COMPOSITION AND METHOD FOR DETECTION OF PRE-METASTATIC SITES - A radio-immunoconjugate for diagnosis and treatment of cancer or metastasis and development of metastasis inhibitory formulations using the same is provided. Also, a radio-immunoconjugate is used as a material indicating a metastatic cancer that has antibody marked with any lanthanum radionuclide and/or gamma, beta or alpha ray emitting radioisotopes targeting a vascular endothelial growth factor receptor (VEGFR) is provided. Such a radio-immunoconjugate is advantageous in that it maintains structural stability of a protein and immune activity thereof and is effectively adsorbed to the surface of vascular endothelial cells. This makes it useful as a pre-metastatic site detection factor. When the radio-immunoconjugate is administered to an animal model with cancer, the radio-immunoconjugate is accumulated in cancerous tissues. Therefore, it is useful for development of radioactive metastasis inhibitory formulations. | 10-01-2009 |
| 20090245453 | DECAY HEAT REMOVAL SYSTEM COMPRISING HEAT PIPE HEAT EXCHANGER - Disclosed herein is a decay heat removal system, including: a decay heat exchanger that absorbs decay heat generated by a nuclear reactor; a heat pipe heat exchanger that receives the decay heat from the decay heat exchanger through a sodium loop for heat removal and then discharges the decay heat to the outside; and a sodium-air heat exchanger that is connected to the heat pipe heat exchanger through the sodium loop and discharges the decay heat transferred thereto through the sodium loop to the outside. According to the decay heat removal system, a heat removal capability can be realized by the heat pipe heat exchanger at such a high temperature at which the safety of a nuclear reactor is under threat, and a cooling effect can be obtained through the sodium-air heat exchanger at a temperature lower than that temperature. | 10-01-2009 |
| 20090232267 | EMERGENCY CORE COOLING SYSTEM HAVING CORE BARREL INJECTION EXTENSION DUCTS - An emergency core cooling system directly injects emergency core cooling water, which is supplied from a high-pressure safety injection pump or a safety injection tank for a pressurized light water reactor, into a reactor vessel downcomer. A pipe connector is completely removed from between each direct vessel injection nozzle and each injection extension duct installed on an outer surface of the core barrel, which are opposite to each other. An emergency core cooling water intake port, through which the water is injected from each direct vessel injection nozzle, is formed on the surface of each injection extension duct facing an axis of each direct vessel injection nozzle. Thereby, a structure in which a jet of the emergency core cooling water flows into the injection extension ducts is adopted in a hydraulic connection fashion. | 09-17-2009 |
| 20090148263 | CABLE-DRIVEN MANIPULATOR - The present invention discloses a cable-driven manipulator comprising an operating unit having a drive motor, and a pulley rotated by the drive motor. An upper arm is coupled, through a joint, to one side of the operating unit. A forearm coupled, through a joint, to the other side of the upper arm by the cable. A gripper of an end effector operably coupled to the forearm, a cable compensation device is installed between the upper arm and the forearm so as to maintain constant the length of the cable that transmits the power of the operating unit to the end effector during the pivoting of the forearm. It is thus possible to prevent the variation of tensile force due to the variation of the length of the cable for operating the end effector during the pivoting of the forearm or the unintended malfunction of the end effector. | 06-11-2009 |
| 20090141851 | NUCLEAR FUEL ROD FOR FAST REACTORS WITH OXIDE COATING LAYER ON INNER SURFACE OF CLADDING, AND MANUFACTURING METHOD THEREOF - Disclosed herein are a nuclear fuel rod for fast reactors, which includes an oxide coating layer formed on the inner surface of a cladding, and a manufacturing method thereof. The nuclear fuel rod for fast reactors, which includes the oxide coating layer formed on the inner surface of the cladding, can increase the maximum permissible burnup and maximum permissible temperature of the metallic fuel slug for fast reactors so as to prolong the its lifecycle in the fast reactors, thus increasing economic efficiency. Also, the fuel rod is manufactured in a simpler manner compared to the existing method, in which a metal liner is formed, and the disclosed method enables the cladding of the fuel rod to be manufactured in an easy and cost-effective way. | 06-04-2009 |
| 20090116607 | Passive cooling and arresting device for molten core material - An apparatus for passively cooling and retaining molten core material discharged from a damaged reactor vessel during a severe accident in the nuclear plant including: a molten core material retention tank to retain molten core material; a compressed gas tank storing high-pressure inert gas; a cooling water storage tank being installed higher than the molten core material retention tank; and a mixing means. The molten core material retention tank includes an outer retention vessel having at least one coolant hole, a porous protection vessel formed at an inside of the outer retention vessel, and a gravel layer formed between the outer retention vessel and the porous protection vessel. The apparatus can be installed in a reactor cavity without changing the compartment structure of a containment building, and makes it possible to prevent a steam explosion during the cooling process for the ultrahigh-temperature molten core material and to secure the reliability of the cooling process. | 05-07-2009 |
| 20090116606 | JOINT TONG APPARATUS FOR RADIATION SHIELDING FACILITY - A joint tong apparatus for a radiation shielding facility. A spherical ball has a through-hole. An inner spherical socket and an outer spherical socket are installed in a hole formed in a partition between a radiation-shielded room and a control room so as to enclose the spherical ball on inner and outer sides. A bar is inserted and coupled into and to the through-hole of the spherical ball. An inner joint assembly has a first housing coupled to a shielded room-side end of the bar and a first pivot member pivotably mounted on a free end of the first housing. An outer joint assembly having a second housing coupled to a control room-side end of the bar and a second pivot member pivotably mounted on a free end of the second housing. The apparatus further includes a tong assembly, a handle assembly, a tong manipulation cable, and a pair of pivot manipulation cables. | 05-07-2009 |
| 20090052607 | Spacer Grid for Close-Spaced Nuclear Fuel Rods - A spacer grid can be applied to close-spaced nuclear fuel rods. The spacer grid is directed to solve the problem in which, as the outer diameter of each nuclear fuel rod increases due to the use of dual-cooled nuclear fuel rods for improving cooling performance and obtaining high combustion and high output power, the gap between the neighboring nuclear fuel rods is narrowed to thus make it impossible to use an existing spacer grid. The spacer grid is a combination of unit grid straps, each of which has supports for supporting each of the nuclear fuel rods set in a narrow array and has a sheet shape, which are combined with each other. The supports are located at positions shifted from the longitudinal central line of each unit grid strap toward sub-channels. | 02-26-2009 |
| 20090048208 | METHOD FOR PRODUCING THE LOW MOLECULAR WEIGHT BETA-GLUCAN BY IRRADIATION AND LOW MOLECULAR WEIGHT BETA-GLUCAN PRODUCED BY THE METHOD - Disclosed herein is a method for the preparation of low-molecular weight beta-glucan by irradiation. The low-molecular weight beta-glucan prepared by irradiation shows a random distribution of all beta-glucan structures, low viscosity and high water solubility, and acts as an excellent antioxidant and to activate immune cells, finding useful application in many fields including the food, medical and cosmetics industries. | 02-19-2009 |
| 20090035201 | PREPARATION METHOD OF TC-99M-LABELED IRON OXIDE NANOPARTICLE AND DIAGNOSTIC IMAGING OR THERAPEUTIC AGENT FOR CANCER DISEASES COMPRISING THE SAME - Disclosed herein are a method of preparing a technetium-99m-labeled iron oxide (Fe | 02-05-2009 |
| 20090016478 | LIQUID TARGET HAVING INTERNAL SUPPORT FOR RADIOISOTOPE PRODUCTION AT CYCLOTRON - An F-18 production target system having an internal support produces F-18 by means of a nuclear reaction of protons and H | 01-15-2009 |
| 20090010377 | INHIBITOR OF CORROSION AND STRESS CORROSION CRACKING CONTAINING NICKEL BORIDE (NiB) IN THE SECONDARY SIDE OF STEAM GENERATOR TUBES IN A NUCLEAR POWER PLANT AND INHIBITING METHOD USING THE SAME - A method of inhibiting corrosion and stress corrosion cracking of a steam generator tube in a nuclear power plant, includes the steps of providing a nuclear power plant having a secondary side feedwater system including a secondary side feedwater of a steam generator tube; and supplying nickel boride to said secondary side feedwater to inhibit corrosion and stress corrosion cracking. | 01-08-2009 |
| 20090001294 | Neutron Coincidence Counter for Non-Destructive Accounting for Nuclear Material and the Handling Thereof - A neutron coincidence counter for non-destructive accounting for a nuclear material according to the present invention comprises an outer case, neutron detectors mounted in the outer case while being surrounded by a moderator, and a basket horizontally movable in the outer case so as to be exposed outside the outer case and having a cavity for receiving a sample container therein. Further, a neutron coincidence counter for non-destructive accounting for a nuclear material according to the present invention comprises an outer case, neutron detectors mounted in the outer case while being surrounded by a moderator, a basket movable in the outer case so as to be exposed outside the outer case and having a cavity for receiving a sample container therein, and an external signal analyzer connected to the detectors through an electrically conductive path. Moreover, at least one facile connector of one-touch connection type is mounted on the electrically conductive path for connecting the detectors to the external signal analyzer, resulting in free removal and replacement of wires connected to the connector. | 01-01-2009 |
| 20080306010 | VACCINE COMPOSITION CONTAINING IRRADIATED OVALBUMIN FOR THE PREVENTION AND TREATMENT OF ALLERGIC DISEASE - The present invention relates to a vaccine composition for the prevention and treatment of allergic disease comprising irradiated ovalbumin as an effective ingredient, more precisely a method for preparing an immunogen of a vaccine for the prevention and treatment of allergic disease using the irradiated ovalbumin which is separated and purified from the albumen of an egg, a vaccine composition for the prevention and treatment of allergic disease comprising the irradiated ovalbumin as an effective ingredient, and a method for the prevention and treatment of allergic disease using the vaccine comprising the irradiated ovalbumin. In the mouse vaccinated with the irradiated ovalbumin, humoral and cell mediated immune responses were both reduced, suggesting that allergic reaction was inhibited. Thus, the composition of the present invention can be effectively used as a vaccine for the prevention and treatment of allergic disease. | 12-11-2008 |
| 20080300444 | OPHTHALMIC APPLICATOR FOR TREATMENT OF PTERYGIUM OR GLAUCOMA USING 32P ALONE OR IN COMBINATION WITH 103Pd - Disclosed is an ophthalmic applicator for the treatment of pterygium or or glaucoma using a radioisotope. It comprises a source volume for containing the radioisotope therein; a filter volume for controlling a radiation dose emitted from the radioisotope; and an encapsulation volume for encompassing the source volume and the filter volume, wherein the radioisotope is pure | 12-04-2008 |
| 20080292041 | Method and system for early sensing of water leakage, through chemical concentration monitoring, in nuclear reactor system using liquid metal and molten salt - A method of early sensing of water leakage, through chemical concentration monitoring, in a nuclear reactor system using a liquid metal and molten salt, the method including: measuring an electrical conductivity and a mass spectrum of a first channel and a second channel of a heat-related device included in the nuclear reactor system using the liquid metal and the molten salt; calculating a first identification value associated with the water leakage in the heat-related device using the measured electrical conductivity; calculating a second identification value associated with the water leakage in the heat-related device using the measured mass spectrum; and sensing the water leakage by comparing a predetermined reference value and a summed identification value, the summed identification value being the sum of the first identification value and the second identification value. | 11-27-2008 |
| 20080286187 | MESOPOROUS SILICA PARTICLES 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. | 11-20-2008 |
| 20080271986 | Method for Isotope Separation of Ytterbium - A method for isotope separation of ytterbium comprises isotope-selective photoionizing of a target isotope by use of a laser, and photoionizing of the target isotope from a metastable state to a continuum state or an auto-ionization state through excited states. The photoionized isotope ions of ytterbium can be separated within an electric field. With the method, it is possible to separate a great amount of ytterbium isotope by use of a simple apparatus while ensuring a highly economic efficiency in comparison with a conventional EM method. | 11-06-2008 |
| 20080242850 | Method of producing chitosan scaffold having high tensile strength and chitosan scaffold produced using the method - Provided are a method of producing a porous chitosan scaffold, the method including: providing an aqueous acidic solution having chitosan and a solvent which does not dissolve the chitosan; and freeze-drying the aqueous acidic solution, wherein the solvent is selected from the group consisting of a C3-C8 aliphatic alcohol having one hydroxy group, ethylene glycol monoethylether, ethylene glycol monobutylether, dioxane, tetrahydrofuran, dimethylcarbonate, acetone and acetonitrile, and a chitosan scaffold produced using the method. | 10-02-2008 |
| 20080219397 | Decay Heat Removal System for Liquid Metal Reactor - A decay heat removal system for a liquid metal reactor in which a decay heat exchanger (DHX) is installed concentrically with an intermediate heat exchanger (IHX) in the same cylinder which separates the DHX and IHX from the reactor pool fluid, and serves to remove the reactor core decay heat. The cylinder surrounds the IHX and DHX, and has an open top portion protruding out of the level of the fluid in a hot pool, a bottom portion connected to a cold pool and a guide pipe for allowing the passage of the fluid from the hot pool into the IHX. The decay heat removal system can remove decay heat immediately after occurrence of an accident, thereby improving the safety of a nuclear plant. | 09-11-2008 |
