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Korea Atomic Energy Research Institute Patents
Assignee:
Korea Atomic Energy Research Institute
Address:
Daejon, KR
No. of patents:
89
Patents:


1 2


Patent Number Title Of Patent Date Issued
7459141 Technetium-99m-labeled organic germanium nanocolloids, method of preparing the same and use ther December 2, 2008
Disclosed relates to organic germanium nanocolloids, to which technetium-99m (.sup.99mTc), a radionuclide, is labeled, method of the same, and a spleen-imaging agent including the same. According to the invention, .sup.99mTc-labeled organic germanium nanocolloids having high labeling
7430267 Multi-core fuel rod for research reactor and manufacturing method thereof September 30, 2008
The present invention relates to a multi-core fuel rod for research reactor and, more particularly, to a multi-core fuel rod for research reactor in which monolithic fuel cores made of uranium-molybdenum alloy are disposed in an aluminum matrix in a multi-core form. The multi-core fu
7390392 Method of in-situ monitoring a reduction of uranium oxides by lithium metal June 24, 2008
Disclosed is a method of in-situ monitoring a reduction process of uranium oxides by lithium metal, wherein a conversion yield of uranium metal from uranium oxides upon production of uranium metal through a reaction of uranium oxides (UO.sub.x, x.ltoreq.3) with lithium metal in the prese
7364070 System and method for real-time remote shopping April 29, 2008
A method for real-time remote shopping using a real-time remote shopping system includes the steps of (a) obtaining the commodity information from a hand-held terminal and registering the information on a customer, (b) sending the shopping request information including the commodity
7242201 Apparatus and method for detecting state of heat exchanger tube July 10, 2007
Provided is an apparatus for concurrently detecting a defect occurring in a heat exchanger tube and a geometric transition of the heat exchanger tube. The apparatus for detecting the state of a heat exchanger tube, including: the first detection unit detecting a defect of the heat ex
7097717 Method and device for collecting particulate contaminants during CO.sub.2 blasting decontaminati August 29, 2006
Disclosed is a method and device for collecting particulate contaminants removed using a CO.sub.2 decontamination medium from an early step of a decontamination process. The device removes particulate contaminants from a contaminated subject by a decontamination stream, and simultaneousl
7094608 Method for measuring lanthanide content dissolved in uranium oxide August 22, 2006
The present invention relates to a method for measuring the content of Lanthanides dissolved in uranium oxide, wherein the Lanthanides content in the nuclear fuel pellet is measured using the thermo gravimetric analysis which measures the weight variation caused by the oxidation and
7090760 Method of reducing spent oxide nuclear fuel into nuclear-fuel metal using LiCl-Li.sub.2O salt, c August 15, 2006
Disclosed are a method of reducing spent oxides nuclear fuel to nuclear-fuel metal, in which metal oxides are reduced to metals using an electrochemical reduction device with LiCl--Li.sub.2O salt as an electrolyte, a cathode electrode assembly used in the method, and a reduction devi
7089805 Average bidirectional flow tube August 15, 2006
An average bidirectional flow tube, including a body having two side plates and upper and lower plates, a partition plate installed to be perpendicular to the side plates of the body so that front and rear ends of the tube are separated from each other, and two pairs of pressure impu
7005084 Thermoluminescent detector of LiF containing Mg, Cu, Na and Si as dopants and its preparation February 28, 2006
The disclosure concerns a pellet type LiF element for a thermoluminescent dosimetry (TLD) and its preparation. More particularly, the disclosure concerns the pellet type LiF element for a thermoluminescent dosimetry (TLD) which includes 0.35.about.0.12% by mole of Mg source; 0.08.abo
6979431 Method for labelling technetium or rhenium using borohydride exchange resin December 27, 2005
A method for labelling a sulfide compound with technetium or rhenium, comprising the reaction of a disulfide compound with pertechnetate or perrhenate in the presence of borohydride exchange resin to obtain a complex of technetium or rhenium with the sulfide compound. The method can
6972108 Device for metallizing uranium oxide and recovering uranium December 6, 2005
Disclosed is a device for metallizing uranium oxide and recovering uranium, which reacts uranium oxide with a lithium metal to product uranium metal powder, and filters the resulting product using a porous filter to separate the uranium metal powder from lithium chloride molten liquid to
6964785 Herbal composition for improving anticancer activity, immune response and hematopoiesis of the b November 15, 2005
Disclosed is a herbal composition comprising a first hot-water extract from a mixture of the plants Angelicae gigantis Radix, Cnidium officinale Makino and Paeonia japonica Miyabe et Takeda at an equal weight ratio, and a polysaccharide fraction as a precipitate formed by adding ethanol
6936240 Method for the preparation of technetium or rhenium complex for radiopharmaceuticals August 30, 2005
The present invention relates to a method of preparing technetium or rhenium complex for radiopharmaceuticals, through reaction of pertechnetate or perrhenate with a ligand in the presence of a reducing agent, wherein the reducing agent is a borohydride exchange resin (BER). The boro
6928133 Pressurized light water reactor having flow converting grooves for emergency core cooling water August 9, 2005
A direct vessel injection-type pressurized light water reactor (DVI-PLWR), in which an emergency core cooling water (ECC) is directly injected into a downcomer of a reactor vessel, is disclosed. In order to reduce the ratio of ECC bypass from the downcomer to a broken area of a cold leg
6902634 Method for manufacturing zirconium-based alloys containing niobium for use in nuclear fuel rod c June 7, 2005
The present invention relates to a method for manufacturing zirconium-based alloys containing niobium with superior corrosion resistance for use in nuclear fuel rod claddings. The method of this invention comprises melting of the alloy, .beta.-forging, .beta.-quenching, hot-working, vacu
6888019 Method of preparing rhenium complex using borohydride exchange resin May 3, 2005
Disclosed is a method of preparing a rhenium complex by use of a borohydride exchange resin, including dissolving perrhenic acid in a solution containing ethylenediamine tetraacetate, mannitol and stannous chloride to obtain a perrhenic acid solution (step 1), which is then mixed wit
6885721 Inhibition method of stress corrosion cracking of nuclear steam generator tubes by lanthanum bor April 26, 2005
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 lanthanum boride as an inhibitor for stress corrosion cracking
6881376 Nuclear fuel body including tungsten network and method of manufacturing the same April 19, 2005
The present invention relates to a nuclear fuel body comprising tungsten network and a method for manufacturing the same, more particularly, a nuclear fuel body in which tungsten network is continuously formed over the entire or some parts of a sintered body and a method for manufacturin
6863409 Apparatus for generating parallel beam with high flux March 8, 2005
Disclosed herein is an apparatus for generating a parallel beam with a high flux. The apparatus of the present invention includes a light source, a first mirror and a second mirror. The light source is positioned at a first focal point of a first ellipse. The first mirror is positioned o
6860317 Method and apparatus for producing uranium foil and uranium foil produced thereby March 1, 2005
Disclosed are a method and an apparatus for producing a uranium foil with fine crystalline granules by forming the foil by the gravitational dropping of molten uranium or uranium alloy and rapidly cooling the foil by the contact with cooling rolls, and a foil produced thereby. In acc
6845138 Spacer grid with hybrid flow-mixing device for nuclear fuel assembly January 18, 2005
A spacer grid with hybrid flow-mixing devices for nuclear fuel bundle is made up of an intersection of a plurality of thin straps at right angles to form a plurality of cells for receiving and supporting fuel rods. Each strap is composed of two types of strap units, called a primary stra
6824668 Method for electroplating Ni-Fe-P alloys using sulfamate solution November 30, 2004
Disclosed is a method of electroplating a Ni--Fe--P alloy using a sulfamate solution and, in particular, a method of electroplating a Ni--Fe--P alloy using a plating solution containing nickel sulfamate, iron sulfamate, phosphorous acid, and a buffer agent. The method is advantageous in
6822249 Radioactive electron emitting microchannel plate November 23, 2004
The present invention relates to a radioactive electron emitting microchannel plate. More particularly, to a radioactive electron generating microchannel plate comprising (a) a pair of parallel substrates; (b) at least one radioactive material layer deposited on an inner surface of t
6811746 Zirconium alloy having excellent corrosion resistance and mechanical properties for nuclear fuel November 2, 2004
The present invention relates to a zirconium alloy having excellent corrosion resistance and mechanical properties and a method for preparing a nuclear fuel cladding tube by zirconium alloy. More particulary, the present invention is directed to a zirconium alloy comprising Zr-aNb-bS
6807246 Lips-type multi-purposed nuclear fuel assembly spacer grid October 19, 2004
A lips-type multi-purposed spacer grid for supporting fuel rods within a nuclear fuel assembly is disclosed. In the spacer grid, the fuel rods are in contact with dimples and water strider-type springs in an equiangular surface contact manner. The spacer grid distributes load, applied to
6782069 In-pile creep test system August 24, 2004
The present invention provides a remote-controlled in-pile creep test system used in in-pile creep tests for measuring and determining mechanical properties of nuclear materials irradiated in research reactors. The in-pile creep test system includes a creep tester vertically installe
6744843 Side-slotted nozzle type double sheet spacer grid for nuclear fuel assemblies June 1, 2004
A side-slotted nozzle type double sheet spacer grid for nuclear fuel assemblies is disclosed. The spacer grid includes intersecting inner strips and four perimeter strips. Each inner strip has unit strip parts, each fabricated by integrating two unit sheet parts together into a single
6721384 Spacer grid with side welding support and flow mixing vane for nuclear reactor fuel assembly April 13, 2004
A spacer grid for nuclear fuel assemblies is disclosed. This spacer grid has a plurality of side weld supports, that is, main supports, upper sub-supports and lower sub-supports, on its interlaced inner straps, with two flow mixing vanes integrally extending upward from each of the main
6714619 Spacer grid with double deflected vanes for nuclear fuel assemblies March 30, 2004
A spacer grid for use in a nuclear fuel assembly has double-deflected vanes that guide an axial flow of coolant around fuel rods and thereby generate swirl flow. The vanes each have a double bend projecting upwardly from first inner straps and projecting toward one fuel rod. The vanes ar
6707872 Spacer grid for nuclear reactor fuel assemblies with grid springs maintaining conformal contact March 16, 2004
A spacer grid used for placing and supporting fuel rods in nuclear reactor fuel assemblies is disclosed. The spacer grid of this invention has a plurality of grid springs designed to have an optimal shape of their vertical support parts, thus reducing fretting wear of the fuel rods c
6699287 Dermal scaffold using alkaline pre-treated chitosan matrix or alkaline pre-treated chitosan and March 2, 2004
Disclosed are a dermal scaffold comprising alkaline pre-treated free amine-containing chitosan matrix, alkaline pre-treated free amine-containing chitosan and alkaline pre-treated collagen mixed matrix, or alkaline pre-treated free amine-containing chitosan and alkaline pre-treated c
6697446 Instrumented capsule for materials irradiation tests in research reactor February 24, 2004
An instrumented capsule for material irradiation tests in research reactors. The instrumented capsule performs an optimum material irradiation test under a testing environment similar to the operational environment of a real reactor. The capsule minimizes the influence of flow-induce
6677748 Method of discriminating through-wall cracks and measuring through-wall length of cracks in nucl January 13, 2004
Disclosed herein is a method of discriminating a through-wall crack and measuring the through-wall length of the crack in a steam generator tube of a nuclear power plant. The method of the present invention is characterized in that the through-wall crack is discriminated and the thro
6650723 Double strip mixing grid for nuclear reactor fuel assemblies November 18, 2003
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, havin
6627908 Radiation source assembly and connector press used in producing such assemblies September 30, 2003
A radiation source assembly and a connector press used in producing such assemblies. In the radiation source assembly, each of the cap connector and the female connector is provided with internal round threads on its pigtail fitting hole, thus engaging with the large-diameter coil of the
6625843 Remote-controlled mobile cleaning apparatus for removal and collection of high radioactive waste September 30, 2003
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 climb
6608881 Duct-type spacer grid with swirl flow vane for nuclear fuel assembly August 19, 2003
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
6586752 CaSO4 based thermoluminescent detector bonded with P-compound and a method for fabricating there July 1, 2003
Disclosed are a CaSO.sub.4 based TL detector bonded with phosphorous compound and a method for fabricating thereof. The CaSO.sub.4 based TL detector can be fabricated by mixing CaSO.sub.4 based TL powder with a phosphorous precursor; molding the mixture powder under pressure; and sin
6556642 Inhibition method of the secondary side stress corrosion cracking in nuclear steam generator tub April 29, 2003
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
6555780 Method for monitoring the size variation and the focus shift of a weld pool in laser welding April 29, 2003
In a laser welding, a laser beam is focused on a workpiece by a focusing lens or lenses. The focusing lens or lenses image an aperture liming the size of the laser beam on the workpiece and the size of focused laser beam is the image size of the aperture on the workpiece at the wavelengt
6555527 Hematopoietic, myeloprotecting, antitumor immune cells generating and radiosensitizing polysacch April 29, 2003
The present invention relates to a polysaccharide composition having the hematopoietic, myeloprotecting, antitumor immune cell generating, and radiosensitizing activities extracted from the roots of Panax ginseng prepared by the steps of: i) obtaining the residue by extracting 1 wt pa
6461666 Radioactive balloon for dilation catheter system and process for preparation thereof October 8, 2002
The present invention relates to a radioactive balloon for angioplasty which is combined with a flexible film containing radionuclides and process for preparation thereof. A balloon dilatation catheter system containing the radioactive balloon can be used in transluminal coronary ang
6443018 Multidirectional fatigue damage indicator September 3, 2002
A multidirectional fatigue damage indicator is disclosed. The fatigue damage indicator is composed of a series of fatigue fuse elements welded to a semicircular assembly frames. The fuse elements have the same fatigue lifetime in each row but have different lifetime from row to row so th
6421407 Nuclear fuel spacer grid with dipper vanes July 16, 2002
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
6379293 Centrifugal extractor for organic phase using a height-adjustable weir and a divert disk April 30, 2002
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
6344625 Method and apparatus for monitoring the size variation and the focus shift of a weld pool in las February 5, 2002
In a laser welding, a laser beam is focused on a workpiece by a focusing lens or lenses. The focusing lens or lenses image an aperture liming the size of the laser beam on the workpiece and the size of focused laser beam is the image size of the aperture on the workpiece at the wavelengt
6325966 Zirconium alloy having high corrosion resistance and high strength December 4, 2001
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
6278759 Spacer grid with multi-springs and dimple vanes for nuclear fuel assemblies August 21, 2001
A nuclear fuel spacer grid, fabricated by intersecting a plurality of grid strips and used for placing and supporting a plurality of elongated fuel rods within a nuclear fuel assembly, is disclosed. The spacer grid of this invention has a plurality of dimple vanes on its grid strips. The
6261516 Niobium-containing zirconium alloy for nuclear fuel claddings July 17, 2001
The invention presented herein relates to a niobium-containing zirconium alloy for use in nuclear fuel cladding. The Zr alloy of this invention with superior corrosion resistance is characterized as comprising an alloy composition as follows:1) niobium (Nb), in a range of 0.8 to 1.2 wt.
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