KOREA ATOMIC ENERGY RESEARCH INSTITUTE Patent applications |
Patent application number | Title | Published |
20160108507 | Chromium-Aluminum Binary Alloy Having Excellent Corrosion Resistance and Method of Manufacturing Thereof - The present disclosure relates to a chromium-aluminum binary alloy with excellent corrosion resistance and a method of producing the same, and more particularly to a chromium-aluminum binary alloy with excellent corrosion resistance, including: 1 to 40% by weight of aluminum (Al), the balance of chromium (Cr), and other unavoidable impurities with respect to a total weight of the alloy, and a method of producing a chromium-aluminum binary alloy with excellent corrosion resistance, the method including: (Step | 04-21-2016 |
20150265667 | Composition Comprising Centipede Grass Extracts or Fractions Thereof as Active Ingredients - The present invention relates to a pharmaceutical composition for preventing or treating diabetes or dementia, comprising centipede grass ( | 09-24-2015 |
20150243384 | COOLING WATER SUPPLY TANK HAVING HEAT MIXING PREVENTION FUNCTION AND PASSIVE HIGH-PRESSURE SAFETY INJECTION SYSTEM AND METHOD USING THE SAME - A passive high-pressure safety injection system includes a compressor which generates high-temperature and high-pressure steam, a cooling water supply tank which supplies cooling water using the compressed steam, a nuclear reactor which receives the cooling water so that the nuclear reactor is maintained in a cooled state, and an internal circulation prevention structure which is provided in the cooling water supply tank and prevents the cooling water from circulating in the cooling water supply tank. | 08-27-2015 |
20150243383 | WATER-AIR COMBINED PASSIVE FEED WATER COOLING APPARATUS AND SYSTEM - Disclosed herein is a water-air combined passive feed water cooling apparatus including a water cooling heat exchanger connected to the inside of a containment building to cool down heat of a steam generator using a water cooling method, a cooling tank including the water cooling heat exchanger therein and storing cooling water condensing main steam generated by the steam generator, an evaporative steam pipe connected to the cooling tank, the evaporative steam pipe, into which steam of the cooling water generated by the water cooling heat exchanger in the cooling tank flows, an air cooling heat exchanger connected to the evaporative steam pipe and cooling down and liquefying the steam flowing into the evaporative steam pipe, and a condensed water collecting pipe for refilling the cooling tank with the steam liquefied by the air cooling heat exchanger. | 08-27-2015 |
20150243382 | PASSIVE CONTAINMENT AIR COOLING DEVICE AND SYSTEM WITH ISOLATED PRESSURE BOUNDARY - Provided is a passive containment air cooling device with an isolated pressure boundary, including a heat exchanger positioned inside and outside a containment, penetrating through an outer wall of the containment to be connected to the containment through a pipe and thus form a closed loop, and including a coolant, an air induction duct circulating air outside the heat exchanger, and a cooled air exhaust unit formed in the air induction duct to increase cooling efficiency of the heat exchanger. | 08-27-2015 |
20150225416 | Novel Rotenone Derivatives and a Use Thereof - The present invention relates to a novel rotenone derivative and a use of the same. Particularly, the present inventors identified the novel rotenoisin A and B which were the compounds with no toxicity and prepared by irradiation with gamma ray onto rotenone represented by the following formula 1 and further confirmed that the novel rotenone derivative significantly inhibited pancreatic lipase activity and preadipocyte differentiation. The novel rotenone derivative of the present invention can be effectively used as a composition for the prevention and treatment of obesity and as a composition for health functional food for the prevention and improvement of obesity: | 08-13-2015 |
20150151011 | Preparation of Technetium-99M Tricarbonyl Labeled Glycine Monomer or Oligomer Containing Probes That Have Biomolecules and Its Application as Imaging Complex-Composition - Disclosed is a technetium-99m-labeled glycine oligomer associated with imaging probes for biomolecules of interest. The glycine oligomer can be readily synthesized in a single process using an automated peptide synthesizer. The technetium-99m tricarbonyl-labeled glycine oligomers can be useful as a radiotracer for gamma or SPECT imaging apparatus. The technetium-99m tricarbonyl-labeled glycine oligomers can be applied to various peptidyl biomolecules such as RGD peptide, somatostatin, neurotensin, etc., and exhibit rapid renal clearance without being excessively retained within the body. | 06-04-2015 |
20150133570 | CROSSLINKED SPEEK CATION EXCHANGE MEMBRANE HAVING IMPROVED CHEMICAL STABILITY BY RADIATION AND METHOD OF PREPARING THE SAME - Provided is a method of preparing a crosslinked sulfonated poly(ether ether ketone) (SPEEK) cation exchange membrane including: preparing a crosslinker mixture of a first crosslinker containing two or more vinyl oxy groups and a second crosslinker containing three or more vinyl groups; preparing a mother liquor containing the crosslinker mixture, a SPEEK polymer substituted with sodium, and a solvent; and casting the mother liquor and then irradiating radiation thereon. | 05-14-2015 |
20150076045 | PURIFICATION METHOD AND APPARATUS FOR RADIOACTIVE WASTEWATER CONTAINING IODINE RADIONUCLIDES - Provided are a purification method and apparatus for radioactive wastewater. The purification method and apparatus for radioactive wastewater according to the present invention, which is a biological purification apparatus for radioactive wastewater containing radioactive iodine, includes: an anoxic tank into which wastewater containing radioactive iodine is introduced; and a microbial purification tank connected to the anoxic tank so as to allow wastewater in an anaerobic state to be introduced and supplied with a metal reducing bacteria source, an electron donor, and a copper ion source, wherein radioactive iodine and copper ions are bound to each other to form copper iodide by metal reducing bacteria, and the formed copper iodide is precipitated in the microbial purification tank, such that the radioactive iodide in the wastewater is removed as sludge. | 03-19-2015 |
20140378733 | Oxidation Decontamination Reagent for Removal of the Dense Radioactive Oxide Layer on the Metal Surface and Oxidation Decontamination Method Using the Same - The present invention provides an oxidative decontamination reagent for removal of the dense radioactive oxide layer on a metal surface, which comprises an oxidizing agent, a metal ion, and an inorganic acid. The oxidative decontamination reagent of the present invention is characteristically prepared by adding a metal ion to the conventional oxidative decontamination reagent containing an oxidizing agent and an inorganic acid. When the oxidative decontamination reagent of the present invention is used, electric potential of the metal parts of the primary system of the nuclear power plant can be regulated as passive potential owing to the added metal ion during the oxidative decontamination of the primary metal part of the nuclear power plant. Therefore, by maintaining electric potential of the metal part as passive potential, local corrosion can be inhibited and at the same time secondary waste can be significantly reduced. | 12-25-2014 |
20140374653 | APPARATUS AND METHOD FOR SEPARATING RADIOACTIVE NUCLIDES AND RECOVERING REFINED SALT FROM LiCl WASTE SALT OR LiCl-KCl EUTECTIC WASTE SALT - There are provided an apparatus and method for separating radioactive nuclides from a waste salt and recovering a refined salt, which are able to maximize process efficiency and operating efficiency of a process of regenerating a waste salt produced during a pyrochemical process of used nuclear fuel by converting the waste salt into a thermally stable form and distilling the waste salt under a reduced pressure using a single apparatus having two top covers which are mountable to replace radioactive nuclides included in the waste salt, and highly improve applicability and utility in a remote operation facility for disposal of a radioactive waste by further simplifying operation/handling compared with conventional processes. | 12-25-2014 |
20140334591 | PASSIVE CONTAINMENT SPRAY SYSTEM - Provided is a passive containment spray system including: a spray coolant storage unit that communicates with a containment accommodating a reactor vessel and maintains equilibrium of pressure between the spray coolant storage unit and the containment; a spray pipe that is installed within the containment in such a manner that when an accident occurs, a coolant supplied from the spray coolant storage unit is sprayed into the containment through the spray pipe due to an increase in pressure within the containment; and a connection pipe one end of which is inserted into the spray coolant storage unit in such a manner as to provide a flow path along which the coolant flows and the other end of which is connected to the spray pipe in such a manner that the coolant is passively supplied to the spray pipe through the connection pipe therein. | 11-13-2014 |
20140334590 | COOLING SYSTEM OF EMERGENCY COOLING TANK AND NUCLEAR POWER PLANT HAVING THE SAME - The present disclosure provides a cooling system of an emergency cooling tank, which enables long-term cooling without refilling cooling water, in case of the change in a quantity of heat transferred to the emergency cooling tank according to a lapse of time upon an occurrence of an accident of a nuclear reactor, and a nuclear power plant having the same. The emergency cooling tank cooling system includes an emergency cooling tank configured to store cooling water therein, the cooling water receiving heat, transferred from a nuclear reactor or a containment, when an accident occurs in the nuclear reactor, a heat exchanging device installed to be exposed to an outside of the emergency cooling tank to operate in air, and configured to externally emit heat by way of a heat exchange between fluid in the emergency cooling tank and the air such that the operation of the emergency cooling tank is continued even without refilling the cooling water, and an opening and closing unit installed at an upper portion of the emergency cooling tank to be located higher than a water level of the cooling water, and configured to be open by a flow of the fluid generated by an evaporation of the cooling water, the flow being formed due to a pressure difference from external air at pressure higher than a preset pressure, such that some of the fluid is externally emitted when a heat load exceeding a cooling capacity of the emergency cooling tank is transferred. | 11-13-2014 |
20140314668 | TECHNETIUM-99M LABELED COMPLEX OF GOLD NANOPARTICLE-GOLD BINDING PEPTIDES, AND METHOD OF MAKING AND USING THE SAME - There is provided a method for preparing a | 10-23-2014 |
20140312536 | EPOXY RESIN COMPOSITION FOR NEUTRON SHIELDING, AND METHOD FOR PREPARING THE SAME - Provided is an epoxy resin composition including a nano-sized radioactive radiation shielding material which has superior shielding effects for against radiation, and to a method for preparing same. In particular, the method for preparing the epoxy resin composition for neutron shielding, includes the steps of: a step of mixing a boron compound powder for absorbing neutrons, optionally a high density metal powder for shielding from against gamma rays and a flame retardant powder, respectively separately or in combination, with an amine-based curing agent to obtain a mixture of a curing agent and a powder; an ultrasonic wave treating step of applying ultrasonic waves to the mixture to coat the surface of the powder with the amine-based curing agent and to disperse the powder in the curing agent; and a dispersing step of mixing and dispersing the amine-based curing agent, that was dispersed and includes the powder treated with ultrasonic waves, in an epoxy resin. | 10-23-2014 |
20140301938 | Method and Apparatus for Separating Carbon and Oxygen Isotopes by Using Optical Fiber Laser - Provided is a method of separating carbon and oxygen isotopes by using a laser. In one preferred embodiment, the method includes performing a photolysis process on formaldehyde including a carbon or oxygen isotope by irradiation with ultraviolet light having a wavelength ranging from 340 nm to 360 nm to generate carbon monoxide having a carbon or oxygen isotope enriched therein and hydrogen, performing a catalytic reaction on the carbon monoxide having a carbon or oxygen isotope enriched therein and the hydrogen to synthesize carbon dioxide (CO | 10-09-2014 |
20140294653 | MARTENSITIC OXIDE DISPERSION STRENGTHENED ALLOY WITH ENHANCED HIGH-TEMPERATURE STRENGTH AND CREEP PROPERTY, AND METHOD OF MANUFACTURING THE SAME - The present application discloses a martensitic oxide dispersion-strengthened alloy having enhanced high-temperature strength and creep properties. The alloy includes chromium (Cr) of 8 to 12% by weight, yttria (Y | 10-02-2014 |
20140234326 | METHOD FOR DECREASING RADIORESISTANCE AND GROWTH, METASTASIS AND INFILTRATION OF CANCER CELLS THROUGH REGULATING EXPRESSION OR ACTIVITY OF TM4SF4 IN NON-SMALL CELL LUNG CANCER - The present invention relates to a pharmaceutical composition or an anticancer agent for preventing and treating non-small cell lung cancer, containing a substance for regulating the expression or activity of transmembrane 4 L six family member 4 (TM4SF4). More specifically, the present invention relates to a use of a substance for regulating the expression or activity of TM4SF4 as an anticancer drug or an anticancer agent with respect to non-small cell lung cancer, wherein it was ascertained that it is possible to decrease the growth, metastasis, and infiltration of adenocarcinoma cells and radioresistance by decreasing the expression of TM4SF4 in adenocarcinoma among non-small cell lung cancers and to decrease the growth, metastasis, and infiltration of the cells and radioresistance by increasing the expression of TM4SF4 in other non-small cell lung cancers except adenocarcinoma. | 08-21-2014 |
20140219409 | MULTI STAGE SAFETY INJECTION DEVICE AND PASSIVE SAFETY INJECTION SYSTEM HAVING THE SAME - The present disclosure may disclose a multi stage safety injection device, including a safety injection tank formed to contain coolant to be injected into a reactor vessel by a gravitational head of water when an accident occurs in which the pressure or water level of the reactor vessel is decreased, a pressure balance line connected to the reactor vessel and safety injection tank to form a pressure balance between the reactor vessel and the safety injection tank, and a set of safety injection lines connected to the safety injection tank and the reactor vessel to inject coolant to the reactor vessel in a pressure balance state between the reactor vessel and the safety injection tank, and connected to the safety injection tank with different heights to reduce a flow rate of coolant injected into the reactor vessel step by step according to the water level reduction of the safety injection tank in order to inject coolant to the reactor vessel at multi stages. | 08-07-2014 |
20140205052 | Chelate Free Chemical Decontamination Reagent for Removal of the Dense Radioactive Oxide Layer on the Metal Surface and Chemical Decontamination Method Using the Same - A chemical decontamination reagent containing a reducing agent, a reductive metal ion, and an inorganic acid is provided to remove a radioactive oxide layer on a metal surface. The reagent can dissolve the radioactive oxide layer on the metal surface effectively at a relatively low temperature and enables a simple process of contacting the reagent to the radioactive oxide, thus economically effective in terms of cost and time required for the process. Since the decontamination does not use a conventional organic chelating agent such as oxalic acid, but the reducing agent as a main substance, the residuals of the reducing agent remained after decontamination can be decomposed and removed with an oxidizing agent. Due to the easy decomposition with the chemical decontamination reagent, secondary wastes can be minimized and the radionuclides remained in the decontamination reagent solution can be removed effectively. | 07-24-2014 |
20140202275 | TWO-FAR END SUPPORTED ACTUATOR MODULE FOR SNAKE ROBOT USING INNER WIRE - A two-far end supported actuator module for a snake robot using an inner wire includes: a module housing having a driving means and a reducer mounted therein, and having a plurality of accommodation portions on an outer surface thereof; an upper cover and a lower cover detachably installed at an upper part and a lower part of the module housing, respectively, wherein the upper cover has a rotation shaft passing hole for passing a rotation shaft therethrough, and the lower cover has a wire passing hole for passing a wire therethrough; a first connection bracket having one side coupled to one accommodation portion of the module housing, and another side coupled to a lower cover of another driving module, and configured to guide the wire thereinto; and a second connection bracket coupled to another accommodation portion of the module housing on the opposite side of the first connection bracket, and another side to which a rotation shaft is inserted to be supported. | 07-24-2014 |
20140185731 | URANIUM DIOXIDE NUCLEAR FUEL PELLET HAVING METALLIC MICROCELLS AND FABRICATING METHOD THEREOF - A uranium dioxide nuclear fuel pellet includes metallic microcells having a high protection capacity for fission products and a high thermal conductivity simultaneously arranged in the nuclear fuel pellet to trap fission products, such that extraction of fission products may be restrained in a normal operation condition and that the temperature of a nuclear fuel may be lowered to enhance the performance of the nuclear fuel, only to restrain extraction of radioactive fission products toward the environment in an accident condition to enhance a stability of the nuclear fuel pellet, and a fabricating method thereof. | 07-03-2014 |
20140185730 | URANIUM DIOXIDE NUCLEAR FUEL PELLET HAVING CERAMIC MICROCELLS AND FABRICATING METHOD THEREOF - A uranium dioxide nuclear fuel pellet has about 50 to about 400 μM (with respect to a 3-dimentional size) microcells formed of a ceramic material having a chemical attraction with fission products generated in the nuclear fuel pellet to absorb and trap the fission products, such that the extraction of the fission product may be retrained in a normal operation condition and that the performance of the nuclear fuel may be enhanced by mitigating PCI. In addition, highly radioactive fission products including Cs and I having a large generation amount or a long half-life enough to affect the environments can be trapped in the pellet in an accident condition, without being released outside. | 07-03-2014 |
20140151215 | Separation and Recovery Device for Liquid Waste Including Radionuclide, and Separation and Recovery Method Using the Same - Provided are a separation and recovery device for a liquid waste including a radionuclide, and a separation and recovery method using the same. Specifically, the present disclosure relates to a separation and recovery device that may effectively separate a liquid waste, such as a waste detergent including a radionuclide, and simultaneously, may prevent the release of tritium and radiocarbon to the outside, and a separation and recovery method using the same. | 06-05-2014 |
20140150515 | Horizontal Type Slitting Apparatus For Decladding of a Fuel Rod - A horizontal type slitting apparatus for decladding of a fuel rod is disclosed. The apparatus optionally includes a plurality of rollers configured to receive, extrude, and transfer a fuel rod, a roller fixing portion configured to fix the rollers by a hydraulic pressure, a slitting portion configured to slit cladding tube of the fuel rod, and a slitter fixing portion configured to fix the slitter portion by a hydraulic pressure. | 06-05-2014 |
20140147423 | PHARMACEUTICAL COMPOSITION CONTAINING FIBULIN-3 PROTEIN AS AN ACTIVE INGREDIENT FOR INHIBITING THE GROWTH OF CANCER STEM CELLS - The present invention relates to fibulin-3 protein and a pharmaceutical composition comprising the fibulin-3 protein as an active ingredient for inhibiting the growth of cancer stem cells. More particularly, in cancer stem cells separated from H460 and A549 cells, which are non-small-cell lung cancer cells, using ALDH1 activity as a marker, fibulin-3 induces the reductions of wnt/β-catenin, MMP2 and 7, which display characteristics of cancer stem cells, thereby decreasing the activated growth and penetration of the cancer stem cells. In addition, the purified fibulin-3 protein inhibits the growth of the non-small-cell lung cancer cell line A549, the breast cancer cell line MDA-MB231, and the cancer stem cell line active ALDH1. Therefore, fibulin-3 can be valuably used as an active ingredient of the pharmaceutical composition for inhibiting the growth of cancer stem cells. | 05-29-2014 |
20140132288 | METHOD FOR MEASURING ELECTRICAL CONDUCTIVITY AND ELECTRICAL CONDUCTIVITY MEASURING SYSTEM USING THE SAME - The present disclosure relates to a method for measuring electrical conductivity and a system for measuring electrical conductivity using the same. The method includes obtaining a cell constant of a conductance cell using a conductivity standard solution, pouring a solution desired to be measured in the conductance cell, and applying predetermined direct current (DC) voltages to electrodes, disposed in the conductance cell, in a manner of changing the predetermined DC voltages in stages at each preset time (t), obtaining resistance of the solution, as a slope, from a linear relationship between the voltage and a peak current, measured for each voltage, and calculating electrical conductivity of the solution using the cell constant and the resistance of the solution. | 05-15-2014 |
20140121361 | NOVEL N3S1 CHELATOR-FOLATE DERIVATIVES, PREPARATION METHOD THEREOF AND COMPOSITION FOR DIAGNOSIS OR TREATMENT OF CANCER CONTAINING THE SAME AS AN ACTIVE INGREDIENT | 05-01-2014 |
20140114112 | CERAMIC INGOT OF SPENT FILTER HAVING TRAPPED RADIOACTIVE CESIUM AND METHOD OF PREPARING THE SAME - A method of preparing a simple ceramic ingot of a spent filter having radioactive cesium trapped therein, and a ceramic ingot of a spent filter having improved properties such as leach resistance, thermal stability, and cesium content are provided. The method includes grinding and mixing a spent filter having cesium trapped therein, adding a solidifying agent, and sintering the spent filter. The method of preparing a ceramic ingot of a spent filter can be useful in preparing the ceramic ingot of the spent filter from only the spent filter by means of simple grinding and sintering, and in preparing the ceramic ingot of the spent filter by adding a small amount of a solidifying agent. The ceramic ingot of the spent filter has a high density and improved thermal stability, and shows improved leach resistance since a leach rate of a radioactive material is remarkably low. Therefore, the spent filter having radioactive cesium trapped therein can be effectively used to prepare a stable ceramic ingot. | 04-24-2014 |
20140112436 | SECURITY CHECKING SYSTEM USING X-RAYS AND NEUTRONS - Provided is a security checking system. The security checking system includes an electron beam acceleration unit for accelerating electron beams having at least one energy intensity, an X-ray guide unit converting the electron beams accelerated by the electron beam acceleration unit into X-rays to guide the converted X-rays into an object, a neutron guide unit, and a detection unit detecting the X-rays and neutrons passing through the object. Thus, nuclear materials within the object may be detected, and also, maintenance/repair costs may be inexpensive to improve economic feasibility. | 04-24-2014 |
20140096646 | TREATMENT METHOD OF SPENT URANIUM CATALYST - The present invention relates to a treatment method of spent uranium catalyst, and more specifically, to a method which can considerably reduce the volume of the spent uranium catalyst to be disposed of and simultaneously minimize secondary wastes that can be generated during the process of treating the spent uranium catalyst. | 04-10-2014 |
20140093733 | POROUS UO2 SINTERED PELLET FOR ELECTROREDUCTION PROCESS, AND PREPARATION METHOD THEREOF | 04-03-2014 |
20140080217 | Uranium Analysis Using Luminescence Enhancing Oxidant and Oxidant Composition - According to the present invention, there is provided a method of determining a concentration of uranium including: a) a primary measuring step of measuring luminescence intensity or luminescence attenuation of uranium (VI) of an oxidant added sample obtained by adding an oxidant composition to a detection target sample; b) a secondary measuring step of adding different volumes of standard solution containing uranium (VI) having a predetermined concentration to a plurality of oxidant added samples, respectively, and then measuring luminescence intensity or luminescence attenuation of uranium (VI) contained in each standard solution added sample; and c) a calculating step of calculating a concentration of uranium (VI) contained in the detection target sample by a standard addition method based on the primary and secondary measurements. With the method for determining a concentration of uranium according to the present invention, the concentration of uranium may be further rapidly and accurately analyzed. | 03-20-2014 |
20140055597 | REMOTE ATTACHING AND DETACHING DEVICE INCLUDING CELL CAMERA - A remote attaching and detaching device is provided, which includes a camera module to substitute a worker's vision in such an environment where the worker's direct access to the in-cell is extremely limited or impossible. In a remote attaching and detaching device including a camera module for monitoring operating environment of a slave arm of a remote robot working in hazardous environment, the remote attaching and detaching device includes a fixing module fixed to a proximity of a gripper provided on the slave arm, and the camera module is attachable to and detachable from the fixing module, and provides visual in-cell information or situation about surroundings of the gripper. | 02-27-2014 |
20140050292 | SEPARATE TYPE SAFETY INJECTION TANK AND INTEGRAL TYPE REACTOR HAVING THE SAME - A separate type safety injection tank comprises: a coolant injection unit connected to a reactor coolant system by a safety injection pipe such that coolant stored therein is injected into the reactor coolant system by a pressure difference from the reactor coolant system when a loss-of-coolant-accident (LOCA) occurs; a gas injection unit connected to the coolant injection unit, and configured to pressurize the coolant injected into the reactor coolant system, by introducing gas stored therein to an upper part of the coolant injection unit in the loss-of-coolant-accident; and a choking device disposed between the coolant injection unit and the gas injection unit, and configured to contract a flow cross-sectional area of the gas introduced to the coolant injection unit, and configured to maintain a flow velocity and a flow rate of the gas introduced to the coolant injection unit as a critical flow velocity and a critical flow rate when a pressure difference between the coolant injection unit and the gas injection unit is more than a critical value. | 02-20-2014 |
20140048020 | TUBE SHEET OF STEAM GENERATOR HAVING ANTICORROSIVE LAYER AND MANUFACTURING METHOD THEREOF - Provided are a tube sheet of a steam generator installed to support a tube of the steam generator, and a manufacturing method thereof, particularly, a tube sheet of a steam generator having an anticorrosive layer and a manufacturing method thereof. | 02-20-2014 |
20140020508 | Method for Manufacturing Metal Nanoparticles Having a Core-Shell Structure with Good Oxidation Stability - Provided is a method for manufacturing metal nanoparticles having a core-shell structure with good oxidation stability, wherein the method comprises the steps of: heating and agitating a core metal precursor solution; mixing a shell metal precursor solution with the heated and agitated core metal precursor solution, and heating and agitating the mixed metal precursor solution; and irradiating the heated and agitated metal precursor solution with radioactive rays. Thus, since yield can be maximized through a simple and environmentally friendly process that does not use a chemical reducing agent, there is no need for a process for removing an added reducing agent, and since a post-heat-treatment of particles is not performed, the manufacturing process is rendered simple and highly economical. | 01-23-2014 |
20140019215 | SYSTEM FOR ASSESSING PROCEDURE COMPLIANCE LEVEL OF HUMAN OPERATORS IN NUCLEAR POWER PLANTS AND METHOD THEREOF - Disclosed are a system for assessing the procedure compliance level of a human operator in a nuclear power plant, which quantitatively detects if the human operator complies with a standard procedure written in an emergency procedure guideline for the nuclear power plant, and a method thereof. The system includes a first recognizing unit attached to each of human operators, a second recognizing unit that is mounted on each of nuclear power equipments and able to make communication with the first recognizing unit, a database storing information of a standard procedure to be performed by the human operator with respect to the nuclear power equipment, and a server that is able to make communication with the second recognizing unit, and assesses the standard procedure stored in the database and an actual procedure performed by the human operator, which is received from the second recognizing unit. | 01-16-2014 |
20140016732 | APPARATUS AND METHOD FOR CONTROLLING CONTROL ROD OF NUCLEAR REACTOR FOR NUCLEAR POWER PLANT - An apparatus and method for safely controlling a control rod of a nuclear reactor for a nuclear power plant is provided. The apparatus may include a first controller to output a signal to insert or withdraw the control rod, a mechanical portion to perform insertion or withdrawal of the control rod in response to the signal output by the first controller, the mechanical portion including a movement process portion, a stop latch to restrain the control rod, a moving latch to move the control rod, and a lift coil to insert or withdraw the control rod, a detector to detect a position or a speed of the control rod when the control rod is inserted or withdrawn, and a brake to stop the control rod by force when the control rod is withdrawn irrespective of an intended control of the control rod. | 01-16-2014 |
20140013873 | CAM-LOCKING DISSIMILAR MATERIAL SLEEVE - Disclosed is a cam-locking dissimilar material sleeve installed on an outer surface of an expansion shaft of an inspection robot inserted into a heat transfer tube of a steam generator for generating nuclear power to inspect the heat transfer tube, the cam-locking dissimilar material sleeve including: a tension part formed of steel and including a plurality of upwardly opened slits and a plurality of downwardly opened slits alternately formed in zigzags and legs formed between the upwardly opened slits and the downwardly opened slits; a plurality of upper contact parts formed of a synthetic resin through injection-molding to surround an upper end of the tension part and surround parts located between the upwardly opened slits; and a plurality of lower contact parts formed of a synthetic resin through injection-molding to surround a lower end of the tension part and surround parts located between the downwardly opened slits. | 01-16-2014 |
20140005407 | METHOD OF PREPARING RADIOISOTOPE NANOSTRUCTURE WITH LIGAND-METAL FRAMEWORK AND APPLICATION | 01-02-2014 |
20130344348 | ZIRCONIUM ALLOY WITH COATING LAYER CONTAINING MIXED LAYER FORMED ON SURFACE, AND PREPARATION METHOD THEREOF - A zirconium alloy with a coating layer formed on a surface comprising a mixed layer, the mixed layer comprises one or more very high temperature oxidation resistant material and zirconium alloy parent material selected from the group consisting of Y | 12-26-2013 |
20130343504 | HEAT EXCHANGER FOR PASSIVE RESIDUAL HEAT REMOVAL SYSTEM - Disclosed is a heat exchanger for a passive residual heat removal system, which improves heat transfer efficiency by expanding a heat transfer area. A heat exchange tube includes a first member connected to a steam pipe through which steam generated from a steam generator of a nuclear reactor circulates, and a second member connected to both of the first member and a feed water pipe used to supply water to the steam generator provided in the nuclear reactor, and the first member has the shape different from that of the second member, thereby expanding the heat transfer area so that the heat transfer efficiency is improved. | 12-26-2013 |
20130302639 | ZIRCONIUM ALLOY FOR IMPROVING RESISTANCE TO OXIDATION AT VERY HIGH TEMPERATURE AND FABRICATION METHOD THEREOF - A zirconium alloy for use in nuclear fuel assemblies is provided, which provides increased resistance against oxidation and corrosion and also improved bonding with parent material, because pure metallic material such as silicon (Si) or chromium (Cr) is evenly coated on the surface of the parent material by plasma spraying. Because the plasma spray coating used to coat the pure metallic material on the zirconium alloy does not require vacuum equipment and also is not limited due to the shape of the coated product, this is particularly useful when evenly treating the surface of the component such as 4 m-long tube or spacer grip arrangement which is very complicated in shape. Furthermore, because the coated zirconium alloy confers excellent resistance to oxidation and corrosion under emergency such as accident as well as normal service condition, both the economic and safety aspects of nuclear fuel are improved. | 11-14-2013 |
20130302244 | METHOD OF PREPARING IODINE SEED FOR TREATING EYE DISEASE OR CANCER, AND IODINE SEED PREPARED THEREBY - The present invention provides a technique for adsorbing I-125 on a support for treating cancer and a method of preparing an I-125 seed using the same. Since a method of preparing iodine according to the present invention uses an intermediate having phosphate-based, oxalate-based, or arsenate-based anions introduced thereinto, the intermediate has a substitution effect of iodine 3 to 5 times higher than that of a typically used intermediate having chlorine anions introduced thereinto. According to the substitution effect, control of a radiation dose may be possible during the manufacturing of an iodine seed and an iodine seed may be prepared within a shorter period of time. Also, since an amount of residual radioactive iodine may be decreased as a result of a large amount of adsorption, an amount of radioactive iodine (I-125) waste may be decreased, and the effect thereof may be also high environmentally. | 11-14-2013 |
20130299470 | Method for oxide dispersion strengthening of metallic material using laser - An oxide dispersion strengthening (ODS) method of a metallic material using a laser is provided, which includes melting a surface of a metallic matrix placed on a movable stage by irradiating a laser onto the surface (step 1), supplying an oxide dispersion strengthening (ODS) powder at a site of the matrix surface which is melt at step 1 (step 2), and cooling the matrix in which the ODS powder is supplied at step 2 (step 3). Because oxide particles are directly supplied into previously-made sheet or tube matrix, fabrication process is simplified, fabrication cost is reduced, and end product is fabricated efficiently. | 11-14-2013 |
20130299161 | DOUBLE PACKER APPARATUS - A double packer apparatus according to embodiments of the present invention may include a first guide unit provided in a borehole within a ground, a second guide unit provided within the ground to cover an external surface of the first guide unit, a packer unit to support the second guide unit in the borehole, and seal a portion of an area provided within the ground, and a photographing unit to enter the first guide unit and photograph the ground, wherein a portion of the external surface of the first guide unit includes a transparent window for photographing the ground. A ground may be investigated directly using a configuration described in the foregoing, thereby contributing to an enhancement of efficiency. | 11-14-2013 |
20130289329 | DECONTAMINATION METHOD OF CLADDING HULL WASTES GENERATED FROM SPENT NUCLEAR FUEL AND APPARATUS THEREOF - The present disclosure relates to a decontamination method and apparatus for cladding hull wastes of spent nuclear fuels, capable of decontaminating a small quantity of spent nuclear fuels remaining on surfaces of the cladding hull wastes and radioactive fission products penetrated into the cladding hulls through an electrochemical dissolution. The method includes inserting the cladding hull waste into an anodic basket, immersing a reference electrode and a cathodic electrode as well as the anodic basket in a molten salt, dissolving a surface of the cladding hull waste by applying a voltage or current to the anodic basket with respect to the cathodic electrode or the reference electrode, removing the anodic basket, and removing a salt remaining on the surface of the cladding hull waste. | 10-31-2013 |
20130266992 | COMPOSITION FOR INCREASING SACCHARIFICATION EFFICIENCY OF BIOMASS, METHOD FOR INCREASING SACCHARIFICATION EFFICIENCY OF BIOMASS AND METHOD FOR PREPARING BIOETHANOL DERIVED FROM BIOMASS ON A LARGE SCALE USING CHAPERONE PROTEIN - The present invention relates to a novel method for increasing saccharification efficiency by adding chaperone protein during saccharification process, more precisely a composition for increasing saccharification efficiency of biomass containing cellulose using peroxiredoxin (Prx) protein and a method for increasing glucose yield by using the same. The conventional saccharification process has the disadvantage of decreasing cellulase activity, suggesting that the high priced saccharogenic enzyme has to be continuously supplied since the saccharogenic enzyme is losing its activity continuously by reducing sugar through the whole saccharification process. Therefore, to increase saccharification efficiency, the present invention provides a method characterized by increasing saccharification efficiency by preventing cellulase from losing its activity throughout the whole saccharification process by using chaperone protein, particularly Prx protein herein, together with cellulase. The method of the present invention, therefore, can overcome the disadvantage of the conventional saccharification process. | 10-10-2013 |
20130264222 | MONITORING METHOD AND SYSTEM OF METAL IONS OR OXYGEN IONS APPLICABLE TO HIGH CONCENTRATION NON-AQUEOUS ELECTROLYTE - A monitoring method of metal ions or oxygen ions applicable to a high concentration non-aqueous electrolyte includes: applying a potential in a non-aqueous electrolyte to obtain current information with respect to the potential; varying the potential applied in the non-aqueous electrolyte containing metal ion concentration or oxygen ion concentration such that the metal ion concentration or the oxygen ion concentration is maintained in spite of the potential being applied; detecting a linear relationship among the concentration, the current, and passed charges in the non-aqueous electrolyte by repeatedly performing the obtaining step and the varying step, while changing the concentration; and calculating metal ion concentration or oxygen ion concentration of the non-aqueous electrolyte in pyroprocessing of the non-aqueous electrolyte by using the linear relationship. Concentration and components of a solute existing in a non-aqueous electrolyte can be measured while an electrowinning process and pyroprocessing is being conducted. | 10-10-2013 |
20130259188 | REVERSE CONICAL LOWER END PLUG FOR AN ANNULAR NUCLEAR FUEL ROD - A lower end plug for an annular nuclear fuel rod includes a support with a great slenderness ratio, a coolant inflow part with an inner inflow space and a plurality of inflow holes in a wall thereof so as to interact with the inflow space, coupled to a lower end of the annular nuclear fuel rod at an upper end thereof, and extending from an upper end of the support in a reverse conical shape such that the inflow space interact with an inner channel of the annular nuclear fuel rod, and a coupler extending from a lower end of the support and coupled with a handing tool of the annular nuclear fuel rod. Thus, although a bottoming phenomenon of the annular nuclear fuel rod occurs, the coolant can be supplied to the inner channel of the annular nuclear fuel rod through the inflow holes of the lower end plug. | 10-03-2013 |
20130243965 | METHOD OF PREPARING GRAPHENE FROM ORGANIC MATERIAL USING RADIATION TECHNIQUE AND GRAPHENE PREPARED USING THE SAME - Provided are a method for preparing grapheme from an organic material using a radiation technique, and graphene prepared using the same, and more particularly, a method of preparing graphene by dissolving an organic material such as polymer, oligomer, or the like, in a solvent to prepare an organic material solution, applying the prepared solution to an upper portion of a substrate to form an organic thin film, introducing a cross-link structure into the organic thin film through irradiation with radiation, and then performing a carbonization process, and graphene prepared using the same. | 09-19-2013 |
20130240805 | Uranium Dioxide Nuclear Fuel Containing Mn and Al as Additives and Method of Fabricating the Same | 09-19-2013 |
20130223582 | FABRICATION METHOD OF BURNABLE ABSORBER NUCLEAR FUEL PELLETS AND BURNABLE ABSORBER NUCLEAR FUEL PELLETS FABRICATED BY THE SAME - A fabrication method of burnable absorber nuclear fuel pellets and burnable absorber nuclear fuel pellets fabricated by the same are provided, in which the fabrication method includes adding boron compound and manganese compound to one or more type of nuclear fuel powders selected from the group consisting of uranium dioxide (UO | 08-29-2013 |
20130220495 | ZIRCONIUM ALLOYS FOR A NUCLEAR FUEL CLADDING HAVING A SUPERIOR OXIDATION RESISTANCE IN A SEVERE REACTOR OPERATION CONDITION AND METHODS OF PREPARING A ZIRCONIUM ALLOY NUCLEAR CLADDING BY USING THEREOF - Disclosed are a zirconium alloy for a nuclear fuel cladding having a good oxidation resistance in a severe reactor operation condition and a method of preparing zirconium alloy nuclear fuel claddings by using thereof. The zirconium alloy includes 1.8 to 2.0 wt % of niobium (Nb); at least one element selected from iron (Fe), chromium (Cr) and copper (Cu); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The amount of Fe is 0.1 to 0.4 wt %, the amount of Cr is 0.05 to 0.2 wt %, and the amount of Cu is 0.03 to 0.2 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under a severe reactor operation condition at an accident condition as well as a normal operating condition of a reactor, thereby improving economic efficiency and safety. | 08-29-2013 |
20130220494 | ZIRCONIUM ALLOYS FOR A NUCLEAR FUEL CLADDING HAVING A SUPERIOR CORROSION RESISTANCE BY REDUCING AN AMOUNT OF ALLOYING ELEMENTS AND METHODS OF PREPARING A ZIRCONIUM ALLOY NUCLEAR FUEL CALDDING USING THEREOF - Disclosed are a zirconium alloy for a nuclear fuel cladding having a good corrosion resistance by reducing an amount of alloying elements and a method of preparing a zirconium alloy nuclear fuel cladding using thereof. The zirconium alloy includes 0.2 to 0.5 wt % of niobium (Nb); 0.2 to 0.6 wt % of iron (Fe); 0.3 to 0.5 wt % of chromium (Cr); 0.1 to 0.15 wt % of oxygen (O); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The total amount of the niobium, the iron and the chromium is 1.1 to 1.2 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under accident conditions as well as normal operating conditions of a reactor, thereby improving economic feasibility and safety. | 08-29-2013 |
20130220493 | ZIRCONIUM ALLOYS FOR A NUCLEAR FUEL CLADDING HAVING A SUPERIOR OXIDATION RESISTANCE IN A REACTOR ACCIDENT CONDITION, ZIRCONIUM ALLOY NUCLEAR FUEL CLADDINGS PREPARED BY USING THEREOF AND METHODS OF PREPARING THE SAME - Disclosed are a zirconium alloy for a nuclear fuel cladding having a good oxidation resistance in reactor accident conditions, a zirconium alloy nuclear fuel cladding prepared by using thereof and a method of preparing the same. The zirconium alloy includes 1.0 to 1.2 wt % of niobium (Nb); at least one element selected from tin (Sn), iron (Fe) and chromium (Cr); 0.02 to 0.1 wt % of copper (Cu); 0.1 to 0.15 wt % of oxygen (0); 0.008 to 0.012 wt % of silicon (Si) and a remaining amount of zirconium (Zr). The amount of Sn is 0.1 to 0.3 wt %, the amount of Fe is 0.3 to 0.8 wt %, and the amount of Cr is 0.1 to 0.3 wt %. A good oxidation resistance of the nuclear fuel cladding may be confirmed under accident conditions as well as normal operating conditions of a reactor, thereby improving economic efficiency and safety. | 08-29-2013 |
20130202075 | WATER-SPRAY RESIDUAL HEAT REMOVAL SYSTEM FOR NUCLEAR POWER PLANT - A residual heat removal system for a nuclear power plant. The residual heat removal system for a nuclear power plant may include an air duct provided on an outside of a reactor containment building, a heat exchanger disposed on an inside of the air duct, a first pipe to transfer, to the heat exchanger, steam generated in a steam generator disposed on an inside of the reactor containment building, and second pipe to transfer, to the steam generator, water condensation that is cooled and condensed in the heat exchanger, wherein the heat exchanger is air-cooled using outside air flowing inside of the air duct. | 08-08-2013 |
20130175719 | Method For Fabricating Porous UO2 Sintered Pellet For Electrolytic Reduction Process For Recovering Metallic Nuclear Fuel Using Continuous Process Of Atmospheric Sintering And Reduction, And Porous UO2 Sintered Pellet Fabricated By The Same - A method for fabricating porous UO | 07-11-2013 |
20130170603 | NUCLEAR FUEL ROD FOR FAST REACTOR - A nuclear fuel rod for a fast reactor includes tubular fuel materials comprising a hollow portion formed therein, a tubular inner pipe inserted into the hollow portion of the tubular fuel materials to prevent collapse of the tubular fuel materials due to combustion of nuclear fuel, a tubular cladding pipe which surrounds the tubular fuel materials, and a liquid metal, or He gas or vacuum applied in a gap between the tubular fuel materials and the tubular cladding pipe. | 07-04-2013 |
20130148774 | POROUS UO2 SINTERED PELLETS AND METHOD FOR FABRICATING POROUS UO2 SINTERED PELLETS AND ELECTROLYTIC REDUCTION USING SAME - A method for fabricating porous UO | 06-13-2013 |
20130146440 | PREPARATION METHOD OF CHROMENONE DERIVATIVES USING RADIATION - A preparation method of chromenone derivatives using radiation is provided. The preparation method exposes commercially-available silybin in reaction solvent to radiation, to thereby concurrently obtain both dehydrosilybin and apigenin compounds, which are chromenone compounds, in a simple reaction step and with high yield. Because the compounds are prepared at economic cost, the preparation method can be advantageously used particularly for the purpose of mass production. Further, in consideration of good cancer cell viability suppression effect thereof, dehydrosilybin and apigenin prepared according to the preparation method can be advantageously used as a pharmaceutical composition for prevention and treatment of cancer. | 06-13-2013 |
20130136223 | METHOD FOR TREATING NEUTRONS GENERATED FROM SPENT NUCLEAR FUEL - A method for treating neutrons generated from spent nuclear fuel is provided, which includes a step of injecting neutron absorption material into the spent nuclear fuel storage water in which cooling function is lost. Accordingly, as the neutron absorption material in the form of particles is injected into a spent nuclear storage pool missing cooling function and deposited on the surface of the spent nuclear fuel, the possibility reaching nuclear criticality is reduced since the neutrons generated from spent nuclear fuel are absorbed. Also, immediate neutron absorbing power is provided upon refilling the pool water into the spent nuclear fuel storage pool in which pool water is depleted. | 05-30-2013 |
20130070887 | REACTOR ADAPTED FOR MITIGATING LOSS-OF-COOLANT ACCIDENT AND MITIGATION METHOD THEREOF - Disclosed are a nuclear reactor adapted for mitigating a loss-of-coolant accident and a mitigation method thereof. The nuclear reactor includes a nuclear reactor vessel, a first pipe part connected to the nuclear reactor vessel to supply or drain fluid, and a first opening/closing part connected to the first pipe part. When the first pipe part is broken, the first opening/closing part closes the first pipe part to stop discharge of coolant. A supplementary coolant injection part is connected to the nuclear reactor vessel through a second pipe part. When the second pipe part is broken, a second opening/closing part closes the second pipe part to stop discharge of coolant. | 03-21-2013 |
20130044853 | FEED WATER AND STEAM HEADER AND NUCLEAR REACTOR HAVING THE SAME - A feed water and steam header equipped to a feed water nozzle or a steam nozzle of a reactor vessel in a steam generator for an integrated nuclear reactor is provided. The feed water and steam header may include a nozzle connection portion connected to a steam nozzle or a feed water nozzle of a reactor vessel, a header flange protruded outward from a lower part of the nozzle connection portion, and a tube connection portion disposed on two pipelines branched from the nozzle connection portion and connected to a tube of the steam generator. | 02-21-2013 |
20130043862 | BIOSENSOR DETECTING THIOL GROUP AND METHOD FOR PREPARING THE BIOSENSOR - There is provided a biosensor for detecting a thiol group and a method of manufacturing the biosensor. In detail, in the method, Au nano particles are manufactured by irradiating radiation (Step 1), a PTh-EDOT/ITO film is manufactured by forming a poly(thiophene-co-3,4-ethylenedioxythiophene) (PTh-EDOT) layer on an indium tin oxide (ITO) coated substrate using cyclic voltammetry (CV) (Step 2) (Step 2); and a Au nano particle modified PTh-EDOT/ITO film is manufactured by dispersing the Au nano particles manufactured in Step 1 onto the PTh-EDOT/ITO film manufactured in Step 2 (Step 3). | 02-21-2013 |
20120304760 | APPARATUS AND METHOD OF MONITORING FLOW OF LIQUID IN PIPE - An apparatus and method for monitoring a flow of liquid in a pipe are provided. The apparatus may include a temperature sensor attached to a pipe of a heat exchanger system to measure a temperature of the pipe, and a controller to determine whether a liquid is present in the pipe, based on a change in the measured temperature. | 12-06-2012 |
20120263268 | PASSIVE HIGH PRESSURE SAFETY INJECTION TANK SYSTEM (HPSIT) FOR RESPONDING TO STATION BLACKOUT (SBO) AND LOSS-OF-COOLANT ACCIDENTS (LOCA) - A high pressure safety injection tank (HPSIT) system includes one safety injection tank (HIT) which replaces a core makeup tank (CMT) and a low pressure (approximately 4.3 Mpa or below) safety injection tank (SIT) and which can shift to and operate on a high pressure (approximately 17 Mpa) operation mode, to enable injection of emergency core coolant into a reactor system both under low pressure (approximately 4.3 Mpa or below) and high pressure (approximately 17 Mpa). | 10-18-2012 |
20120244055 | Adsorbents for Radioisotopes, Preparation Method Thereof, and Radioisotope Generators Using the Same - Disclosed is a novel adsorbent for use in a | 09-27-2012 |
20120244041 | APPARATUS FOR RECOVERING RESIDUAL SALT FROM THE REDUCED URANIUM METAL - Disclosed herein is an apparatus for recovering residual salt from the reduced uranium metal. The apparatus comprising: an evaporating chamber accommodating mixed molten salt or a reduced uranium metal; a heating furnace surrounding the evaporating chamber to heat the mixed molten salt in the evaporating chamber; an insulator disposed over the evaporating chamber to block heat generated from the evaporating chamber, and including an evaporating pipe in a center thereof to move vapor generated from the evaporating chamber; a receiver disposed over the insulator to collect powder formed by condensing and solidifying vapor passing through the evaporating pipe; and a condenser disposed over the receiver to prevent the vapor passing through the evaporating pipe from leaking out of the apparatus. | 09-27-2012 |
20120183111 | PROMPT GAMMA-RAY DETECTION APPARATUS FOR ANALYZING CHEMICAL MATERIALS USING FEMTOSECOND PULSE LASER-INDUCED NEUTRONS - Disclosed herein is a prompt gamma-ray detection apparatus for analyzing chemical materials using femtosecond pulse laser-induced neutrons, which can be effectively used in the nondestructive inspection of various materials, such as metals, coal, cement, radioactive materials and the like as well as explosives and chemical materials, and which can provide better measurement results for the analysis of basic materials, and a method of measuring prompt gamma-rays using the apparatus. The prompt gamma-ray detection apparatus is advantageous because it can non-destructively analyze the elements in a chemical sample using a femtosecond pulse laser-induced neutron generator that solves the problems of an atomic reactor for research or a radioactive isotope as a neutron radiation source. | 07-19-2012 |
20120176603 | METHOD OF QUANTITATIVELY ANALYZING URANIUM IN AQUEOUS SOLUTIONS - Disclosed herein is a method of quantitatively analyzing uranium in an aqueous solution, the method comprising measuring Raman scattering intensity of water and luminescence intensity of uranium standard solutions having various concentrations (Operation 1); calculating a ratio of the uranium luminescence intensity to the Raman scattering intensity of water for each uranium concentration and plotting a calibration curve therethrough (Operation 2); and measuring Raman scattering intensity of water and uranium luminescence intensity of an unknown sample, calculating a ratio of the measured intensities and determining a uranium concentration thereof by using the calibration curve (Operation 3). | 07-12-2012 |
20120168636 | METHOD FOR PROCESSING 3D DISTRIBUTION IMAGE OF RADIATION SOURCE AND SYSTEM USING THE SAME - A system for processing three dimensional (3D) distribution image of a radiation source and a processing method using the same are provided. The system includes an image measuring unit comprising a plurality of position sensitive detectors to measure the radiation source, a signal amplifying unit which receives signals from the image measuring unit and amplifies the received signals into an electric signal, a mode selecting unit that receives the electric signal and selects a detection mode and outputs a corresponding mode signal, a data storage unit which stores the signals as a series of items, a data converting unit which converts the data stored at the data storage unit into interactive data, an image reconstructing unit which reconstructs the converted data into the 3D distribution image, and a display unit which displays the 3D distribution image received from the reconstructing unit. | 07-05-2012 |
20120165594 | SOLIDIFICATION METHOD OF RADIOACTIVE WASTE ACCOMPANYING CHLORIDE RECYCLING OR RADIOACTIVE IODIDE REMOVING AND THE DEVICE THEREOF - The present invention relates to a method and apparatus for solidifying radioactive waste accompanying chlorine recycling or radioactive iodine removal. The present invention provide a method and apparatus for treating radioactive waste composed of volatile metal halide with high corrosiveness at a high temperature through a solidifying system including crushing, mixing/dehalogenating and sintering. In the inventive method and apparatus for solidifying radioactive waste, a dechlorination process by using a dehalogenation material is performed on highly corrosive metal salt under an oxidizing atmosphere by using a method of controlling a temperature on the surface of a reactor, and solidification is carried out by removing radioactive iodine while reusing chlorine contained in an exhaust gas. Accordingly, the generated amount of total waste can be reduced, and therefore the inventive method and apparatus can be usefully used in preparing a solidified body with high durability. | 06-28-2012 |
20120153091 | APPARATUS FOR CABLE MANAGEMENT SYNCHRONIZED WITH TELESCOPIC MOTION - Disclosed herein is an apparatus for cable management synchronized with telescopic motion. The apparatus is configured such that cables for transmitting power or signals to a manipulator provided on a lower end of a telescopic tube and for receiving signals therefrom are wound or unwound in response to expansion or contraction of the telescopic tube. Moreover, the apparatus is configured such that the cables are prevented from being displaced from the correct positions, a noise is prevented from being generated, and the tension of each cable is adjusted even when it is in the clamped state. | 06-21-2012 |
20120145287 | ZIRCONIUM ALLOY COMPOSITIONS HAVING EXCELLENT CORROSION RESISTANCE BY THE CONTROL OF VARIOUS METAL-OXIDE AND PRECIPITATE AND PREPARATION METHOD THEREOF - Disclosed herein are a zirconium alloy composition, which exhibits excellent corrosion resistance by varying the kinds of metal oxides and controlling the size of precipitates of the composition, including: 1.05˜1.45 wt % of Nb; one or more selected from the group consisting of 0.1˜0.7 wt % of Fe and 0.05˜0.6 wt % of Cr; and residual Zr, and a method of preparing the same. The zirconium alloy composition exhibits excellent corrosion resistance by controlling the kinds and amounts of the elements included in the zirconium alloy composition and the heat-treatment temperature and thus varying the kinds of metal oxides formed during an oxidation process and controlling the size of precipitates of the zirconium alloy, so that it can be usefully used as a raw material for nuclear fuel cladding tubes, spacer grids, nuclear reactor internals and the like of a light-water reactor or a heavy-water reactor in a nuclear power plant. | 06-14-2012 |
20120140876 | PORTABLE INDUSTRIAL LIMITED ANGLE GAMMA-RAY TOMOGRAPHY SCANNING SYSTEM - Provided is a diagnostic method and system capable of applying tomography to industrial long cylindrical process systems, such as a pipe line, which are difficult to diagnose using existing medical or industrial computed tomography (CT) scanners. Existing industrial X-ray CT scanners cannot be used for such a pipe that is attached to the process system and thus cannot be placed on the turntable, and existing image diagnostic apparatuses of a fan beam type, a collimated beam type, etc. having a stereotyped structure are next to impossible to move and use for undetachable process systems and their peripheral devices. To solve these problems, there is provided a gamma-ray tomography scanning system that is capable of being directly attached to a pipe in operation and measuring a cross section of the pipe. | 06-07-2012 |
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 |