...that in the early 1940s GE engineer James Wright was charged with a task of utmost importance to the war effort: develop a cheap substitute for rubber that could be used to produce tires, gas masks and a whole host of military gear. Wright tackled the task diligently -- and wound up inventing Silly Putty.
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| Application No. | Application Title | Issue Date |
| 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... | 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 so... | 04/05/2012 |
| 20120053857 | CABLE FOR INSPECTING HEAT TUBES AND METHOD OF ANALYZING INSERTION FORCE OF CABLE A heat tube inspection cable and a method of analyzing an insertion force of the cable are disclosed. The heat tube inspection cable includes a sensor unit configured to detect a defect in a heat tube, a plurality of segment units each configured to comprise a body part... | 03/01/2012 |
| 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 radiati... | 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 f... | 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... | 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 (UO2) or plutonium dioxide (PuO2) having ceramic properties with metallic thorium (Th), in order to enable ... | 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 di... | 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 an... | 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 ... | 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 lase... | 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... | 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... | 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 shap... | 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 li... | 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 ... | 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 cu... | 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 ... | 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 ... | 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 ... | 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 imp... | 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 ... | 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 gre... | 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 ra... | 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 electro... | 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 perform... | 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 cha... | 12/02/2010 |
| 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... | 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 o... | 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... | 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 99Mo/99mTc generator, which is a medical diagnostic radioisotope generator, and in a 188W/188Re generator, which is a therapeutic radioisotope generator. The adsorbent composed of su... | 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 ... | 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 v... | 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 per... | 07/08/2010 |
| 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 ... | 06/24/2010 |
| 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... | 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 (1) of a liquid-metal cooled fast reactor includes nuclear fuel ... | 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 inte... | 05/27/2010 |