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Небесная энциклопедия

Космические корабли и станции, автоматические КА и методы их проектирования, бортовые комплексы управления, системы и средства жизнеобеспечения, особенности технологии производства ракетно-космических систем

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Мониторинг СМИ

Мониторинг СМИ и социальных сетей. Сканирование интернета, новостных сайтов, специализированных контентных площадок на базе мессенджеров. Гибкие настройки фильтров и первоначальных источников.

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19-01-2012 дата публикации

STEREO X-RAY INSPECTION APPARATUS AND METHOD FOR FORMING THREE-DIMENSIONAL IMAGE THROUGH VOLUME RECONSTRUCTION OF IMAGE ACQUIRED FROM THE SAME

Номер: US20120014506A1
Автор:
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A stereo x-ray inspection apparatus comprising:a feeding unit for feeding an object to be inspected;an x-ray generator installed at one side of the feeding unit to irradiate x-rays to the object; andfirst and second detectors for detecting x-rays passing through the object after being irradiated from the x-ray generator to the object.2. The stereo x-ray inspection apparatus according to claim 1 , wherein the x-ray generator and the first detector are disposed to be opposite to each other along a perpendicular line extending between the x-ray generator and the first detector claim 1 , and the second detector is disposed on a horizontal line perpendicular to the perpendicular line claim 1 , along with the first detector claim 1 , so that the x-ray generator claim 1 , the first detector and the second detector are arranged to form a right-angled triangular shape.3. The stereo x-ray inspection apparatus according to claim 2 , further comprising a horizontal feeding unit for horizontally moving the second detector.4. The stereo x-ray inspection apparatus according to claim 3 , further comprising:a rotating unit for rotating the second detector in accordance with a position to which the second detector is moved by the horizontal feeding unit, ...

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Номер записи: 1
01-03-2012 дата публикации

CABLE FOR INSPECTING HEAT TUBES AND METHOD OF ANALYZING INSERTION FORCE OF CABLE

Номер: US20120053857A1
Автор:
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

A heat tube inspection cable and a method of analyzing an insertion force of the cable are disclosed. The heat tube inspection cable includes a sensor unit configured to detect a defect in a heat tube, a plurality of segment units each configured to comprise a body part and a wheel part rotatably connected to the body part, a signal cable configured to helically pass through the body part of each of the plurality of segment units to transmit electric signal from the sensor unit, and a wire configured to pass through the body part of each of the plurality of segment units to. 1. A heat tube inspection cable comprising:a sensor unit configured to detect a defect in a heat tube;a plurality of segment units each configured to comprise a body part and a wheel part rotatably connected to the body part;a signal cable configured to helically pass through the body part of each of the plurality of segment units to transmit electric signal form the sensor unit; anda wire configured to pass through the body part of each of the plurality of segment units to keep the linear configuration of the plurality of segment units like a bead necklace and to provide axial and bending strength.2. The heat tube inspection cable of claim 1 , wherein the body part comprises a cable insertion part helically winding in a length direction of the body part.3. The heat tube inspection cable of claim 2 , wherein the cable insertion part of each of the plurality of segment units continues to a neighboring cable insertion part of a neighboring segment unit.4. The heat tube inspection cable of claim 1 , wherein a length of the body part is adjusted corresponding to a radius of curvature of the heat tube.5. The heat tube inspection cable of claim 1 , wherein the wheel part comprises a first wheel part claim 1 , and a second wheel part spaced apart from the first wheel part by a predetermined interval claim 1 , andthe second wheel part is in a position rotated by a predetermined angle from the first ...

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Номер записи: 2
08-03-2012 дата публикации

Surface modification method of fluoropolymers by electron beam irradiation and the fabrication of superhydrophobic surfaces using the same

Номер: US20120056108A1
Автор: Chan-Hee Jung, Eun Je Lee, In-Tae Hwang, Jae-Hak Choi, Sung Oh Cho, Young-Chang Nho
Принадлежит: Korea Atomic Energy Research Institute KAERI, Korea Hydro and Nuclear Power Co Ltd

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.

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Номер записи: 3
05-04-2012 дата публикации

METHOD OF DETECTING IMPURITIES IN HIGH TEMPERATURE AQUEOUS SOLUTION AND APPARATUS OF DETECTING IMPURITIES FOR THE SAME

Номер: US20120081133A1
Автор: Hwang Jaesik, SONG Kyuseok, YEON Jei-Won, Yun Myung Hee
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. 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.2. The method as set forth in claim 1 , wherein the noble metal electrode is one selected from the group consisting of platinum (Pt) claim 1 , gold (Au) claim 1 , rhenium (Re) claim 1 , ruthenium (Ru) claim 1 , rhodium (Rh) claim 1 , palladium (Pd) and iridium (Ir) claim 1 , or alloys thereof.3. The method as set forth in claim 1 , wherein the noble metal electrode is one selected from the group consisting of platinum (Pt) claim 1 , gold (Au) and palladium (Pd) claim 1 , or alloys thereof.4. The method as set forth in claim 1 , wherein the noble metal electrode is platinum (Pt) or an alloy thereof.5. The method as set forth in claim 1 , wherein the reducing agent is one selected from the group consisting of dissolved hydrogen claim 1 , ammonia and hydrazine (NH) claim 1 , or mixtures thereof.6. The method as set forth ...

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Номер записи: 4
03-05-2012 дата публикации

HIGH Cr FERRITIC/MARTENSITIC STEELS HAVING AN IMPROVED CREEP RESISTANCE FOR IN-CORE COMPONENT MATERIALS IN NUCLEAR REACTOR, AND PREPARATION METHOD THEREOF

Номер: US20120106693A1
Автор: Chan Bock Lee, Chang Hee Han, Dohee Hahn, Jong Hyuk Baek, Jun Hwan Kim, Sung Ho Kim, Tae Kyu Kim, Woo Gon Kim, Yeong-II Kim
Принадлежит: Korea Atomic Energy Research Institute KAERI, Korea Hydro and Nuclear Power Co Ltd

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).

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Номер записи: 5
17-05-2012 дата публикации

Electronic scale having function of compensating for air pressure changes in glove box

Номер: US20120123721A1
Автор: Hong-Joo AHN, Jei-Won Yeon, Jong-Yun Kim, Kyuseok Song, Sang Eun Bae, Yong Joon Park
Принадлежит: Korea Atomic Energy Research Institute KAERI, Korea Hydro and Nuclear Power Co Ltd

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.

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Номер записи: 6
14-06-2012 дата публикации

ZIRCONIUM ALLOY COMPOSITIONS HAVING EXCELLENT CORROSION RESISTANCE BY THE CONTROL OF VARIOUS METAL-OXIDE AND PRECIPITATE AND PREPARATION METHOD THEREOF

Номер: US20120145287A1
Автор: Choi Byoung Kwon, Jeong Yong Hwan, KIM Hyun Gil, Kim Jun Hwan, LEE Myung Ho, Park Jeong Yong, PARK Sang Yoon
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. 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 , comprising: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; andresidual Zr.2. The zirconium alloy composition according to claim 1 , further comprising: 0.12 wt % of Sn.3. The zirconium alloy composition according to claim 1 , wherein the zirconium alloy composition comprises: 1.15˜1.25 wt % of Nb claim 1 , 0.12˜0.45 wt % of Fe claim 1 , and residual Zr.4. The zirconium alloy composition according to claim 3 , further comprising: 0.12 wt % of Sn.5. The zirconium alloy composition according to claim 1 , wherein the zirconium alloy composition comprises: 1.15˜1.25 wt % of Nb claim 1 , 0.05˜0.45 wt % of Cr claim 1 , and residual Zr.6. The zirconium alloy composition according to claim 5 , further comprising: 0.12 wt % of Sn.7. The zirconium alloy composition according to claim 1 , wherein the zirconium alloy ...

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Номер записи: 7
05-07-2012 дата публикации

METHOD FOR PROCESSING 3D DISTRIBUTION IMAGE OF RADIATION SOURCE AND SYSTEM USING THE SAME

Номер: US20120168636A1
Автор: HA Jang Ho, Kim Han Soo
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A system for processing three dimensional (3D) distribution image of a radiation source , comprising:an image measuring unit which comprises a plurality of position sensitive detectors to measure the radiation source, the plurality of position sensitive detectors each having a devoted channel set therefore, and being arranged in a circularly fashion around the radiation source;a signal amplifying unit which receives signals indicative of energy magnitude and location of the radiation source from the image measuring unit and amplifies the received signals into an electric signal;a mode selecting unit which receives the electric signal generated at the signal amplifying unit, and selects a detection mode according to the energy magnitude and the location and outputs a corresponding mode signal;a data storage unit which stores the signals indicative of the energy magnitude, time of radiation generation, and location of the radiation source, and the signal received from the mode selecting unit as a series of items;a data converting unit which converts the data stored at the data ...

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Номер записи: 8
19-07-2012 дата публикации

PROMPT GAMMA-RAY DETECTION APPARATUS FOR ANALYZING CHEMICAL MATERIALS USING FEMTOSECOND PULSE LASER-INDUCED NEUTRONS

Номер: US20120183111A1
Автор:
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A prompt gamma-ray detection apparatus for analyzing chemical materials using femtosecond pulse laser-induced neutrons , which is 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 provides measurement results for the analysis of basic materials , comprising:a femtosecond pulse laser device having beam energy characteristics causing a D-D nuclear fusion reaction;a vacuum chamber for producing neutrons using a femtosecond pulse laser-induced D-D nuclear fusion reaction caused by the femtosecond pulse laser device;a target mount configured to cylindrically mount a plastic target containing deuterium;a rotor for rotating the cylindrical plastic target containing deuterium to continuously generate femtosecond pulse laser-induced neutrons;an outer cover for minimizing the emission of neutrons from the entire outer side of the target mount excluding a laser admission part;a chemical sample mount for mounting a chemical sample that is an object to be measured;a lithium polyethylene port through which specific gamma-rays pass, the specific gamma-rays being ...

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Номер записи: 9
27-09-2012 дата публикации

Adsorbents for Radioisotopes, Preparation Method Thereof, and Radioisotope Generators Using the Same

Номер: US20120244055A1
Автор: Hyeon Young Shin, Hyon Soo Han, Jong Sub Lee, Jun Sig LEE, Kang Duk JANG, Kwang Jae Son, Soon Bog HONG, Ul Jae Park
Принадлежит: Korea Atomic Energy Research Institute KAERI

Disclosed is a novel adsorbent for use in a 99 Mo/ 99m Tc generator, which is a medical diagnostic radioisotope generator, and in a 188 W/ 188 Re generator, which is a therapeutic radioisotope generator. The adsorbent composed of sulfated alumina or alumina-sulfated zirconia exhibits adsorption capacity superior to that of conventional adsorbents, and is stable and is thus loaded in a dry state in an adsorption column so that the radioisotope 99 Mo or 188 W can be adsorbed. Thus, it is possible to miniaturize the column, and such a miniaturized column is small, convenient to use, and highly efficient, and extracts a radioisotope satisfying the requirements for pharmaceuticals, and thus can be useful for radioisotope generators extracting 99m Tc or 188 Re.

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Номер записи: 10
21-02-2013 дата публикации

Biosensor detecting thiol group and method for preparing the biosensor

Номер: US20130043862A1
Автор: Sang Hyun Park, Yeon Jun Jeong
Принадлежит: Korea Atomic Energy Research Institute KAERI

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).

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Номер записи: 11
21-02-2013 дата публикации

FEED WATER AND STEAM HEADER AND NUCLEAR REACTOR HAVING THE SAME

Номер: US20130044853A1
Автор: CHOI Shun, HAN In Su, JANG Ki Jong, KIM Dong Ok, KIM Tae Wan, LEE Gyu Mahn, PARK Hyun Jin
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A feed water and steam header of a steam generator in an integrated nuclear reactor , the feed water and steam header comprising: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; anda tube connection portion disposed on two pipelines branched from the nozzle connection portion and connected to a tube of the steam generator.2. The feed water and steam header of claim 1 , wherein the tube connection portion is branched in two directions with respect to the nozzle connection portion at a predetermined angle.3. The feed water and steam header of claim 2 , wherein the tube connection portion is branched at 90°.4. The feed water and steam header of claim 1 , wherein the tube connection portion comprises a tube sheet to which a plurality of tubes are connected.5. The feed water and steam header of claim 1 , wherein a fastening portion is formed at an end of the nozzle connection portion to be fastened to the steam nozzle or the feed water nozzle.6. An integrated reactor comprising:a reactor vessel;a steam generator disposed in the reactor vessel and wound with a plurality of tubes in a coil form;a feed water nozzle disposed at a lower part of the reactor vessel to introduce cooling water into the steam generator;a steam nozzle disposed at an upper part of the reactor vessel to exhaust steam generated ...

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Номер записи: 12
21-03-2013 дата публикации

REACTOR ADAPTED FOR MITIGATING LOSS-OF-COOLANT ACCIDENT AND MITIGATION METHOD THEREOF

Номер: US20130070887A1
Автор: Bae Hwang, Chung Young Jong, Hwang Young Dong, Kim Keung Koo, Kim Young In, Lee Won Jae, Park Cheon Tae, Yoon Jung, Zee Sung Kyun
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A nuclear reactor adapted for mitigating a loss-of-coolant accident , comprising:a nuclear reactor vessel:a first pipe part connected to the nuclear reactor vessel to supply or drain fluid; anda first opening/closing part connected to the first pipe part,wherein when the first pipe part is broken, the first opening/closing part closes the first pipe part to stop discharge of coolant.2. The nuclear reactor of claim 1 , wherein the nuclear reactor vessel is connected to the first pipe part through a flange to reinforce a connected portion therebetween claim 1 , andthe first opening/closing part is disposed on the flange.3. The nuclear reactor of claim 1 , further comprising a supplementary coolant injection part that is connected to the nuclear reactor vessel to compensate for the loss of coolant through a broken line of the first pipe part.4. The nuclear reactor of claim 3 , wherein the supplementary coolant injection part is connected to the nuclear reactor vessel through a second pipe part claim 3 , anda second opening/closing part is connected to the second pipe part to close the second pipe part to stop discharge of coolant when the second pipe part is broken.5. The nuclear reactor of claim 4 , wherein the nuclear reactor vessel is connected to the second pipe part through a flange to ...

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Номер записи: 13
13-06-2013 дата публикации

PREPARATION METHOD OF CHROMENONE DERIVATIVES USING RADIATION

Номер: US20130146440A1
Автор: Jeong Il Yun, JIN Chang Hyun, RYU Hyung-Won
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 2. The preparation method as set forth in claim 1 , wherein the reaction solvent comprises C-Clower alcohol containing dimethyl sulfoxide.3. The preparation method as set forth in claim 1 , wherein the reaction solvent comprises methanol or ethanol containing dimethyl sulfoxide.4. The preparation method as set forth in claim 1 , wherein the radiation is selected from the group consisting of gamma radiation claim 1 , electron radiation and X radiation.5. The preparation method as set forth in claim 1 , wherein the radiation is emitted at a dose of 100-500 kGy.6. The preparation method as set forth in claim 1 , wherein the step of exposing the dissolved chroman compound of chemical formula 3 to radiation is performed at a temperature ranging between 0° C. and room temperature. This application claims priority from Korean Patent Application No. 10-2011-0131687, filed on Dec. 9, 2011, in the Korean Intellectual Property Office, the contents of which are incorporated herein by reference in its entirety1. Field of the InventionThe present invention relates to a preparation method of chromenone derivatives using radiation.2. Description of the Related ArtSilybin is major active component of a thistle of the genus , a flowering plant of the daisy family ...

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Номер записи: 14
04-07-2013 дата публикации

NUCLEAR FUEL ROD FOR FAST REACTOR

Номер: US20130170603A1
Автор: BAEK Jong-Hyuk, CHEON Jin-Sik, Kim Jun-Hwan, Lee Byoung-Oon, Lee Chan-Bock
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A nuclear fuel rod for a fast reactor , comprising: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; anda liquid metal charged in a gap between the tubular fuel materials and the tubular cladding pipe, whereinthe tubular inner pipe comprise a collecting space formed therein to collect fissile products which are generated due to combustion of the nuclear fuel.2. The nuclear fuel rod of claim 1 , further comprising a plenum formed on an upper end of the tubular fuel materials to collect the fissile products generated due to combustion of the nuclear fuel.3. The nuclear fuel rod of claim 1 , wherein the tubular fuel materials comprises at least one element selected from a group consisting of uranium (U) claim 1 , plutonium (Pu) claim 1 , zirconium (Zr) claim 1 , americium (Am) claim 1 , neptunium (Np) claim 1 , and curium (Cm).4. The nuclear fuel rod of claim 1 , wherein a cross section fraction occupied by the tubular fuel materials takes up 50% to 90% of the total cross section of the fuel rod.5. The nuclear fuel rod of claim 1 , wherein an outer circumference of the tubular inner pipe and an inner circumference of the tubular fuel materials are brought into close contact with each other claim 1 , so that the tubular inner pipe supports the tubular ...

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Номер записи: 15
11-07-2013 дата публикации

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

Номер: US20130175719A1
Автор: Jang Jin Park, Jin-Myeong Shin, Sang-Ho Na
Принадлежит: Korea Atomic Energy Research Institute KAERI

A method for fabricating porous UO 2 sintered pellets to be fed into an electrolytic reduction process for the purpose of metallic nuclear fuel recovery is provided, which includes forming a powder containing U 3 O 8 by oxidizing a spent nuclear fuel containing uranium dioxide (UO 2 ) (step 1), fabricating U 3 O 8 green pellets by compacting the powder formed in step 1 (step 2), and fabricating UO 2 sintered pellets by sintering the U 3 O 8 green pellets fabricated in step 2 at 1000 to 1600° C., in an atmospheric gas, and cooling the same for reduction, by changing the atmosphere to a reducing atmospheric gas (step 3). The porous UO 2 sintered pellets can be fabricated, which do not have any defects. The volatile fission products are sufficiently removed from the fabricated porous UO 2 sintered pellet, the O/U ratio is 2.00, the permeation of the electrolyte during reduction is facilitated, and the electrolytic reduction velocity increases.

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Номер записи: 16
08-08-2013 дата публикации

WATER-SPRAY RESIDUAL HEAT REMOVAL SYSTEM FOR NUCLEAR POWER PLANT

Номер: US20130202075A1
Автор: Baek Won Pil, KWON Tae Soon, Song Chul Hwa, Yang Joon Eon
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A residual heat removal system for a nuclear power plant , the residual heat removal system comprising: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; anda second pipe to transfer, to the steam generator, condensation water 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.2. The residual heat removal system of claim 1 , further comprising:a cooling water supply module to supply a cooling water to the heat exchanger,wherein the heat exchanger is water-cooled by spraying the cooling water on the heat exchanger.3. The residual heat removal system of claim 2 , the air duct comprising:a first shut-off valve to selectively open and close one end of the air duct,wherein the heat exchanger is water-cooled by being submerged in a cooling water supplied from the cooling water supply module when the first shut-off valve is closed.4. The residual heat removal system of claim 2 , wherein the cooling water supply module is located at a higher elevation when compared to the heat exchanger so as to supply the cooling water to the heat exchanger through use of a water ...

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Номер записи: 17
29-08-2013 дата публикации

FABRICATION METHOD OF BURNABLE ABSORBER NUCLEAR FUEL PELLETS AND BURNABLE ABSORBER NUCLEAR FUEL PELLETS FABRICATED BY THE SAME

Номер: US20130223582A1
Автор: KIM Dong-Joo, Kim Jong-Hun, KIM Keon-Sik, KOO Yang-Hyun, Rhee Young Woo, Yang Jae-Jo
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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), plutonium dioxide (PuO) and thorium dioxide (ThO) and mixing the same (step 1), compacting the mixed powder of step 1 into compacts (step 2), and sintering the compacts of step 2 under hydrogen atmosphere (step 3). According to the fabrication method, sintering can be performed under hydrogen atmosphere at a temperature lower than the hydrogen atmosphere sintering that is conventionally applied in the nuclear fuel sintered pellet mass production, by adding sintering additives such as manganese oxide or the like. 1. A fabrication method of burnable absorber nuclear fuel pellets , comprising:{'sub': 2', '2', '2, 'adding boron compound and manganese compound to one or more type of nuclear fuel powders selected from the group consisting of uranium dioxide (UO), plutonium dioxide (PuO) and thorium dioxide (ThO) and mixing the same (step 1);'}compacting the mixed powder of step 1 into compacts (step 2); andsintering the compacts of step 2 under hydrogen atmosphere (step 3).2. The fabrication method of claim 1 , wherein the boron compound of step 1 is one or more types of compounds selected from the group consisting of boron carbide (BC) claim 1 , titanium diboride (TiB) claim 1 , zirconium diboride (ZrB) and boron nitride (BN).3. The fabrication method of claim 1 , wherein the boron compound of step 1 is boron nitride (BN).4. The fabrication method of claim 1 , wherein the manganese compound of step 1 is one or more types of compounds selected from the group consisting of manganese oxide (MnO) claim 1 , manganese dioxide (MnO) claim 1 , manganese sulfide claim 1 , manganese fluoride claim 1 , and manganese chloride.5. The fabrication method of ...

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Номер записи: 18
03-10-2013 дата публикации

Reverse conical lower end plug for an annular nuclear fuel rod

Номер: US20130259188A1
Автор: Chang Hwan Shin, Dong Seok Oh, Hyung Kyu Kim, Jae-Yong Kim, Kang-Hee Lee, Kun Woo Song, Kyung-Ho Yoon, Tae Hyun Chun, Wang Kee In, Young Ho Lee
Принадлежит: Korea Atomic Energy Research Institute KAERI, Korea Hydro and Nuclear Power Co Ltd

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.

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Номер записи: 19
10-10-2013 дата публикации

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

Номер: US20130266992A1
Автор: Bai Hyoungwoo, Chung Byung Yeoup, HONG Sung-Hyun, Lee Seungsik
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A method for increasing saccharification efficiency of biomass including the step of treating chaperone protein and saccharogenic enzyme or saccharogenic enzyme composition together to biomass.2. The method for increasing saccharification efficiency of biomass according to claim 1 , wherein the biomass includes cellulose.3. The method for increasing saccharification efficiency of biomass according to claim 1 , wherein the chaperone protein is peroxiredoxin protein having the amino acid sequence represented by SEQ. ID. NO: 3.4. The composition for increasing saccharification efficiency of biomass according to claim 1 , wherein the saccharogenic enzyme is selected from the group consisting of cellulase claim 1 , beta-glycosidase claim 1 , and xylanase.5. The method for increasing saccharification efficiency of biomass according to claim 1 , wherein the saccharogenic ...

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Номер записи: 20
31-10-2013 дата публикации

Decontamination method of cladding hull wastes generated from spent nuclear fuel and apparatus thereof

Номер: US20130289329A1
Автор: Chang Hwa Lee, Geun Il Park, Kweon Ho KANG, Min Ku Jeon
Принадлежит: Korea Atomic Energy Research Institute KAERI

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.

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Номер записи: 21
14-11-2013 дата публикации

DOUBLE PACKER APPARATUS

Номер: US20130299161A1
Автор: Choi Jong Won, JI Sung Hoon, KOH Yong Kwon, WON Kyeong Sik
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A double packer apparatus , comprising: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 to seal a portion of an area provided within the ground;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,the second guide unit includes an open portion that is oriented to face the transparent window of the first guide unit, andan injection unit constructed to inject water into the open portion of the second guide unit.2. The double packer apparatus of claim 1 , wherein the first guide unit and the second guide unit have hollow guide pipes having different diameters on concentric circles.3. (canceled)4. (canceled)5. A double packer apparatus claim 1 , comprising:a first guide unit provided in a borehole within a ground, and having a transparent window on a portion of an external surface;a second guide unit, provided within the ground to cover an external surface of the first guide unit, in which a portion of an area facing the transparent window ...

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Номер записи: 22
14-11-2013 дата публикации

METHOD OF PREPARING IODINE SEED FOR TREATING EYE DISEASE OR CANCER, AND IODINE SEED PREPARED THEREBY

Номер: US20130302244A1
Автор: Choi Kang Hyuk, CHOI Sun Ju, LEE Jin-Hee, Nam Sung-Soo, Son Kwang Jae
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A method of preparing an iodine seed for treating eye disease or cancer , the method comprising:forming an intermediate by introducing one type of anions selected from the group consisting of phosphates, oxalates, and arsenates into a surface of a support (step 1); andsubstituting the anions of the intermediate of step 1 with I-125 (step 2).2. The method as set forth in claim 1 , wherein the forming of the intermediate in step 1 is performed by introducing a support into a solution claim 1 , in which one type of anions selected from the group consisting of phosphates claim 1 , oxalates claim 1 , and arsenates is dissolved claim 1 , and stirring.3. The method as set forth in claim 1 , wherein the forming of the intermediate in step 1 is performed after cleaning the support with distilled water or nitric acid.4. The method as set forth in claim 1 , wherein the phosphate-based anions of step 1 are formed of one selected from the group consisting of phosphoric acid (HPO) claim 1 , lithium phosphate (LiPO) claim 1 , lithium dihydrogen phosphate (LiHPO) claim 1 , ...

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Номер записи: 23
26-12-2013 дата публикации

Heat exchanger for passive residual heat removal system

Номер: US20130343504A1
Автор: Keung Koo Kim, Seung Yeop Yoo, Young In Kim, Young Min Bae
Принадлежит: Korea Atomic Energy Research Institute KAERI

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.

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Номер записи: 24
02-01-2014 дата публикации

Method of preparing radioisotope nanostructure with ligand-metal framework and application

Номер: US20140005407A1
Автор: Jin Ho MOON, Jong Bum Kim, Min Seok Oh, Seong-Ho Choi, Sung Hee Jung
Принадлежит: Korea Atomic Energy Research Institute KAERI

This invention relates to a method of preparing a radioisotope nanostructure having a ligand-metal framework, and a radioisotope nanostructure prepared thereby. The method of preparing the radioisotope nanostructure of the invention has a simple preparation process and can thus be applied to mass production of a radioisotope nanostructure. Also, because this radioisotope nanostructure is nano-sized spherical particles and has no reactive group, it can be easily dispersed in a fluid, and this nanostructure is physically and chemically stable and thus can be utilized as a radioisotope tracer in the fields of refineries, chemistry, cement, agriculture, water resources, marine, etc. Furthermore, this nanostructure can be used for diagnosis and/or treatment in medical fields, and can be applied to checking whether a nanomaterial is harmful. In addition, this nanostructure is expected to be applicable in a variety of fields using radioisotopes.

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Номер записи: 25
16-01-2014 дата публикации

CAM-LOCKING DISSIMILAR MATERIAL SLEEVE

Номер: US20140013873A1
Автор: JEONG Kyung Min, SEO Yong Chil, SHIN Ho Cheol
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. 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 vapor generator for generating nuclear power to inspect the heat transfer tube , the dissimilar material sleeve comprising: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 to form legs 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; anda 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.2. The cam-locking dissimilar material sleeve of claim 1 , wherein the tension part has a plurality of through-holes at upper and lower ends thereof so ...

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Номер записи: 26
16-01-2014 дата публикации

APPARATUS AND METHOD FOR CONTROLLING CONTROL ROD OF NUCLEAR REACTOR FOR NUCLEAR POWER PLANT

Номер: US20140016732A1
Автор: Baang Dane, Kim Young Ki, Lee Jong Bok, Park Je Yun
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. An apparatus for controlling a control rod of a nuclear reactor for a nuclear power plant , the control rod to be inserted into or withdrawn from the nuclear reactor , the apparatus comprising: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 comprising a movement process portion disposed at an upper end of the control rod, a stop latch to restrain the control rod by an electromagnetic interaction with the movement process portion, a moving latch to move the control rod by restraining the control rod by an electromagnetic interaction with the movement process portion, and a lift coil to insert or withdraw the control rod by lifting or lowering the moving latch fixed to the moving process portion;a detector to detect a position or a speed of the control rod when the control rod is inserted or withdrawn by the mechanical portion; anda brake to stop the control rod by force when the control rod is withdrawn irrespective of an intended control of the control rod.2. The apparatus of claim 1 , wherein the ...

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Номер записи: 27
16-01-2014 дата публикации

Passive safety injection system using safety injection tank

Номер: US20140016733A1
Автор: Cheon Tae Park, Hark Rho Kim, Joo Hyung Moon, Jun Lee, Keung Koo Kim, Seung Yeob YOO, Soo Jai Shin, Suhn CHOI, Tae Wan Kim, Won Jae Lee, Young In Kim, Young Min Bae
Принадлежит: Korea Atomic Energy Research Institute KAERI

A passive safety injection system includes a containment, a reactor installed in the containment, safety injection tanks installed in the containment, a safety injection line between the reactor or a reactor coolant system and each of the safety injection tanks to guide water, which is stored in the safety injection tank, into the reactor when a water level in the reactor is reduced due to a loss of coolant accident, and a pressure balance line between the reactor or the reactor coolant system and the safety injection tank to guide high-temperature steam from the reactor into the safety injection tank upon the loss of coolant accident. The safety injection line has an orifice and a check valve thereon, and the pressure balance line has an orifice and isolation valves thereon. The water in the safety injection tank stably flows into the reactor for many hours.

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Номер записи: 28
20-02-2014 дата публикации

SEPARATE TYPE SAFETY INJECTION TANK AND INTEGRAL TYPE REACTOR HAVING THE SAME

Номер: US20140050292A1
Автор: BAE Young Min, Kim Keung Koo, Kim Young In, YOON Ju Hyeon
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A separate type safety injection tank , comprising: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 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; anda 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 ...

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Номер записи: 29
03-04-2014 дата публикации

POROUS UO2 SINTERED PELLET FOR ELECTROREDUCTION PROCESS, AND PREPARATION METHOD THEREOF

Номер: US20140093733A1
Автор: Bae Sang-Oh, Hwang Hyong Jin, Ji Chul Goo, Kim Ki Hong, Na Sang-Ho, Park Jong-man, Song Dae-Yong
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Porous UOsintered pellets to be fed into an electrolytic reduction process for the purpose of metallic nuclear fuel recovery, include one or more hollow spaces formed from the surfaces toward the interiors thereof. When the porous UOsintered pellets are used in the electrolytic reduction process, the efficiency increases. 119-. (canceled)20. A porous UOsintered pellet to be fed into an electrolytic reduction process for the purpose of metallic nuclear fuel recovery , the porous UOsintered pellet comprising one or more hollow spaces formed in a surface of the pellets , the one or more , hollow spaces extending inwardly from the surface toward interiors thereof.21. The porous UOsintered pellet as set forth in claim 20 , wherein the porous UOsintered pellet is configured in a shape of a cylindrical or polygonal pillar.22. The porous UOsintered pellet as set forth in claim 20 , wherein the one or more hollow spaces pass through the porous UOsintered pellet in a lengthwise direction.23. A method for fabricating porous UOsintered pellets to be fed into an electrolytic reduction process for the purpose of metallic nuclear fuel recovery claim 20 , the porous UOsintered pellets having one or more hollow spaces formed in a surface of the pellets claim 20 , the one or more claim 20 , hollow spaces extending inwardly from the surface toward interiors thereof claim 20 , the method comprising the steps of:{'sub': 3', '8', '2, 'forming a powder containing UOby oxidizing spent nuclear fuel containing uranium dioxide (UO) (step 1);'}compacting the powder formed in step 1 into green pellets with hollow spaces formed therein (step 2); and{'sub': '2', 'fabricating the porous UOsintered pellets by sintering the green pellets fabricated in step 2 and reducing the same in a reducing atmospheric gas (step 3).'}24. The method as set forth in claim 23 , further comprising a step of homogenizing the powder formed in step 1 prior to compacting the powder in step 2.25. The method as set forth ...

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Номер записи: 30
13-01-2022 дата публикации

SENSOR TUBE FOR HUMIDITY SENSOR AND HUMIDITY SENSOR ASSEMBLY USING SAME

Номер: US20220011190A1
Автор: CHOI Hae Seob, EUH Dong Jin, Kim Woo Shik, KIM Yeon Sik, KWON Tae Soon
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

A sensor tube according to the present invention comprises: a tubular body for connecting two connection pipes to each other, wherein the two connection pipes are connected to a humidity sensor, so that the connection pipes transfer steam to the humidity sensor by using circulating air or air discharged from the humidity sensor flow in the connection pipes; and a cover surrounding at least a part of the outer surface of the body to prevent foreign substances having a predetermined size or larger from passing, wherein the body is formed as a porous sintered body which allows stream to be introduced from the outside of the body into the body and be transferred by the circulating air. 1. A sensor tube comprising:a tubular main body configured to connect two connecting tubes, the two connecting tubes being connected with a humidity sensor and configured to deliver steam to the humidity sensor using circulation air or allow the circulation air released from the humidity sensor to flow; anda cover configured to surround at least part of an outside surface of the main body to prevent entrance/exit of foreign matter having a predetermined size or larger,wherein the main body is formed of a porous sintered body configured to allow the steam to be introduced into the main body from outside the main body and carried by the circulation air.2. The sensor tube of claim 1 , wherein the outside surface of the main body includes:connecting areas formed adjacent to opposite ends of the main body so as to be connected with end portions of the connecting tubes; andan intermediate area, the intermediate area being an area other than the connecting areas, andwherein the cover is disposed to surround the intermediate area.3. The sensor tube of claim 1 , wherein a plurality of fine pores through which the steam passes are formed in the porous sintered body.4. The sensor tube of claim 3 , wherein the porous sintered body is a sintered body formed by sintering metal powder.5. The sensor tube ...

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Номер записи: 31
05-01-2017 дата публикации

PASSIVE COOLING SYSTEM OF CONTAINMENT BUILDING AND NUCLEAR POWER PLANT COMPRISING SAME

Номер: US20170004892A1
Автор: BAE Young Min, HA Jae Joo, Han Hun Sik, KANG Kyung Jun, Kim Keung Koo, KIM Tae Wan, Kim Young In, Kim Young Soo, MOON Joo Hyung, Park Cheon Tae, RYU Seung Yeob, SHIN Soo Jai, YOON Ju Hyeon
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present invention discloses a passive cooling system of a containment building, to which a plate-type heat exchanger is applied. A passive cooling system of a containment building comprises: a containment building; a plate-type heat exchanger provided to at least one of the inside and the outside of the containment building and comprising channels respectively provided to the both sides of a plate so as to be arranged dividedly from each other such that the plate-type heat exchanger carries out mutual heat exchange between the internal atmosphere of the containment building and a heat exchange fluid while maintaining a pressure boundary; and a pipe connected to the plate-type heat exchanger by penetrating the containment building so as to form the path of the internal atmosphere of the containment building or the heat exchange fluid. 1. A passive containment building cooling system , comprising:a containment building;a plate type heat exchanger installed on at least one place of an inside and an outside of the containment building, and provided with channels arranged to be distinguished from one another at both sides of a plate to exchange heat between atmosphere within the containment building and heat exchange fluid from each other while maintaining a pressure boundary; anda line connected to the plate type heat exchanger through the containment building to form a flow path of the atmosphere within the containment building or the heat exchange fluid.2. The passive containment building cooling system of claim 1 , wherein the channels are formed in such a manner that a flow resistance of the inlet region is relatively larger than that of a main heat transfer region connected between an inlet region and an outlet region to mitigate flow instability due to two phase flow.3. The passive containment building cooling system of claim 2 , wherein the inlet region is formed with a smaller width than that of the main heat transfer region claim 2 , and formed to extend a ...

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Номер записи: 32
17-01-2019 дата публикации

Treatment Method for Volume Reduction of Spent Uranium Catalyst

Номер: US20190019590A1
Автор: AHN Byung-Gil, CHUNG Dong Yong, Kim Kwang-Wook, Lee Keun-Young, SEO Bum Kyoung
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present invention relates to a volume reduction treatment method of a spent uranium catalyst. According to the volume reduction treatment method of a spent uranium catalyst of the present invention, the disposal cost of the spent uranium catalyst can be reduced and the utilization of the repository can be improved since the method can significantly reduce the volume of the final disposal waste of the spent uranium catalyst. 1. A treatment method of a spent uranium catalyst comprising the following steps:selectively dissolving the support component by immersing the spent uranium catalyst in an alkali solution (step 1);separating the dissolution solution and the undissolved solid materials in the step 1 by solid-liquid separation (step 2);selectively precipitating the silicon ions included in the dissolution solution as silicon dioxide (step 3);separating the silicon dioxide generated in step 3 by solid-liquid separation and its purification (step 4);precipitating uranium ions as uranium phosphate by adding phosphate to the residual solution separated in the step 4 (step 5);separating the uranium phosphate generated in step 5 by solid-liquid separation (step 6);mixing the undissolved solid materials separated in step 2 with the precipitate of uranium phosphate separated in step 6 and then adding a glassification agent thereto, followed by heat-treatment to fix the mixture in the form of a glass-ceramic composite medium (step 7).2. The treatment method of a spent uranium catalyst according to claim 1 , wherein the spent uranium catalyst of step 1 has a form in which USbMO(M is one or more materials selected from the group consisting of Fe claim 1 , Al claim 1 , Mo claim 1 , V claim 1 , and Bi; w claim 1 , x claim 1 , y claim 1 , and z indicate the molar ratio of the elements constituting the oxide) is supported on a silicon dioxide support.3. The treatment method of a spent uranium catalyst according to claim 1 , wherein the alkali solution of step 1 is one or more ...

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Номер записи: 33
23-01-2020 дата публикации

INTEGRATED MONITERING SYSTEM FOR RADIOLOGICAL SURVEILLANCE OF GROUNDWATER AND OPERATION METHOD THEREOF

Номер: US20200025949A1
Автор: BAIK Min-Hoon, KOH Yong-kwon, KWON Jang-Soon, LEE Jae-Kwang
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

An integrated monitoring system for radiological surveillance of groundwater and an operation method thereof are disclosed. The integrated monitoring system for radiological surveillance of groundwater around a nuclear facility according to an embodiment of the present disclosure may include a field monitoring system configured to monitor sectionally isolated groundwater characteristics by establishing a multiple packer system at each depth in groundwater around the nuclear facility, and measure whether or not radioactive contamination has occurred at each depth in groundwater pumped through an automatic branching apparatus connected to a sectional groundwater flow pipe isolatedly disposed at the each depth, and convert field measurement data acquired based on the measurement result into a DB and transmit the DB to a remote monitoring apparatus over a network, and the remote monitoring apparatus configured to remotely control the field monitoring system, and receive the DB-based field measurement data from the field monitoring system, and analyze the received field measurement data to predict a radioactive contaminant source, and provide a contaminant plume showing the distribution characteristics of contaminants in 3D graphic processing. 1. An integrated monitoring system for radiological surveillance of groundwater around a nuclear facility , comprising:a field monitoring system configured to monitor sectionally isolated groundwater characteristics by establishing a multiple packer system at each depth in groundwater around the nuclear facility, and measure whether or not radioactive contamination has occurred at each depth in groundwater pumped through an automatic branching apparatus connected to a sectional groundwater flow pipe isolatedly disposed at the each depth, and convert field measurement data acquired based on the measurement result into a DB and transmit the DB to a remote monitoring apparatus over a network; andthe remote monitoring apparatus ...

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Номер записи: 34
24-04-2014 дата публикации

SECURITY CHECKING SYSTEM USING X-RAYS AND NEUTRONS

Номер: US20140112436A1
Автор: Jang Kyu Ha, Kang Hee Yung, Kim Byung Nam, LEE Byung Cheol, Lee Sang Hyun, Li Yong Gui
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A security checking system comprising:an electron beam (eBeam) acceleration unit to accelerate an eBeam having at least one energy level;an X-ray guide unit to convert the eBeam accelerated by the eBeam acceleration unit into X-rays and guide the X-rays to an object including a cargo;a neutron guide unit to convert the eBeam accelerated by the eBeam acceleration unit into neutrons and guide the neutrons to the object; anda detection unit to detect the X-rays and the neutrons passed through the object.2. The security checking system of claim 1 , wherein the X-ray guide unit and the neutron guide unit are arranged parallel with each other to face the eBeam acceleration unit.3. The security checking system of claim 1 , wherein the eBeam acceleration unit comprises:a first acceleration unit to accelerate a first eBeam having at least one energy level toward the X-ray guide unit; anda second acceleration unit to accelerate a second eBeam having at least one energy level which is different from the energy level of the first eBeam toward the neutron guide unit.4. The security check system of claim 1 , whereinthe X-ray guide unit comprises at least one first conversion unit to convert the eBeam into the X-rays and at least one first collimator unit to guide the X-rays to the object,the neutron guide unit comprises at least one second conversion unit to convert the eBeam into the neutrons ...

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Номер записи: 35
23-01-2020 дата публикации

PASSIVE REACTOR CAVITY COOLING SYSTEM

Номер: US20200027596A1
Автор: JO Changkeun, KIM Eungseon, KIM Minhwan, LIM Hongsik, Park Byungha
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

A passive reactor cavity cooling system according to the present invention includes: a reactor cavity formed between a reactor vessel and a containment structure enclosing the reactor vessel; a first cooling system to control external air to sequentially pass through an air falling pipe and an air rising pipe provided in the reactor cavity, so that residual heat of a core transferred to the reactor cavity is discharged to the atmosphere; a second cooling system having a water cooling pipe disposed in an inner space of the containment structure or in a wall of the containment structure to discharge the residual heat of the core transferred to the reactor cavity to outside; and a functional conductor having an insulating property in a normal operation temperature range of the reactor and a heat transfer property in an accident occurrence temperature range of the reactor which is a higher temperature environment than the normal operation temperature range, wherein the air falling pipe and the water cooling pipe are disposed behind the air rising pipe with respect to a direction viewed from the reactor vessel, and the functional conductor is disposed between the air falling pipe and the air rising pipe. 1. A passive reactor cavity cooling system , comprising:a reactor cavity formed between a reactor vessel and a containment structure enclosing the reactor vessel;a first cooling system to control external air to sequentially pass through an air falling pipe and an air rising pipe provided in the reactor cavity, so that residual heat of a core transferred to the reactor cavity is discharged to the atmosphere;a second cooling system having a water cooling pipe disposed in an inner space of the containment structure or in a wall of the containment structure to discharge the residual heat of the core transferred to the reactor cavity to outside; anda functional conductor having an insulating property in a normal operation temperature range of the reactor and a heat transfer ...

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Номер записи: 36
23-01-2020 дата публикации

NUCLEAR FUEL PELLET HAVING ENHANCED THERMAL CONDUCTIVITY AND METHOD OF MANUFACTURING THE SAME

Номер: US20200027602A1
Автор: Kim Dong Seok, KIM Dong-Joo, Kim Jong-Hun, KIM Keon-Sik, OH JangSoo, YANG Jae-Ho
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Disclosed are a nuclear fuel pellet having enhanced thermal conductivity and a method of manufacturing the same, the method including (a) a step of manufacturing a mixture including a nuclear fuel oxide powder and a thermally conductive plate-shaped metal powder; and (b) a step of molding and then heat-treating the thermally conductive plate-shaped metal powder to have an orientation in a horizontal direction in the mixture, thereby forming a pellet. 1. A method of manufacturing a nuclear fuel pellet having enhanced thermal conductivity , the method comprising:(a) a step of manufacturing a mixture comprising a nuclear fuel oxide powder and a thermally conductive plate-shaped metal powder; and(b) a step of molding and then heat-treating the thermally conductive plate-shaped metal powder to have an orientation in a horizontal direction in the mixture, thereby forming a pellet.2. The method according to claim 1 , wherein the nuclear fuel oxide powder of the step (a) has an average particle size of 0.1 μm to 50 μm.3. The method according to claim 1 , wherein the nuclear fuel oxide powder of the step (a) comprises one or more selected from the group comprising uranium dioxide (UO) claim 1 , plutonium dioxide (PuO) claim 1 , and thorium dioxide (ThO).4. The method according to claim 1 , wherein the thermally conductive plate-shaped metal powder of the step (a) has a ratio of average width to thickness of 10 to 300.5. The method according to claim 1 , wherein the thermally conductive plate-shaped metal powder of the step (a) has an average width of 1 μm to 900 μm and a thickness of 0.1 μm to 3 μm.6. The method according to claim 1 , wherein the thermally conductive plate-shaped metal powder of the step (a) has an average aspect ratio of planes of granules of 1 to 5.7. The method according to claim 1 , wherein the thermally conductive plate-shaped metal powder of the step (a) comprises one or more selected from the group comprising molybdenum (Mo) claim 1 , chromium (Cr) ...

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Номер записи: 37
11-02-2016 дата публикации

Voloxidizer with double reactor for spent fuel rods decladding and double reactor for use in the same

Номер: US20160042821A1
Автор: Geun-Il Park, In-Tae Kim, Jae-won Lee, Young-Hwan Kim
Принадлежит: Korea Atomic Energy Research Institute KAERI

A voloxidizer with a double reactor for spent fuel rods decladding of the present invention includes a reactor module into which spent fuel rods are loaded, the reactor module including a reactor having a dual structure; a heater module for heating the reactor module; and a drive module for providing a driving force to the reactor module. A double reactor utilized in a voloxidizer for spent fuel rods decladding includes an internal reactor into which spent fuel rods are loaded; and an external reactor formed on an outer circumferential surface of the internal reactor. Here, a first transport part and a second transport part are formed on inside surfaces of the internal reactor and the external reactor, respectively, and the spent fuel rods are moved by the first transport part and the second transport part and oxidized when the internal reactor and the external reactor are rotated.

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Номер записи: 38
07-02-2019 дата публикации

METHOD FOR PREPARING HERBAL COMPOSITION HAVING INCREASED FAT-SOLUBLEPOLYPHENOL CONTENT, HERBAL COMPOSITION PREPARED THEREBY AND USE THEREOF

Номер: US20190038690A1
Автор: Cho Hyang Hee, Jo Sung-Kee, Jung Uhee, LEE Ho Yong, Park Hae Ran
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present invention relates to a method for preparing an herbal composition with increased fat-soluble polyphenols, an herbal composition prepared by the method, and a use of the composition. The herbal composition with increased fat-soluble polyphenols of the present invention is characterized by the significantly increased content of fat-soluble polyphenols including decursin, compared with the herbal composition of comparative example, and also demonstrates a significant anti-oxidative activity, immune cell activating effect, and cancer cell growth inhibitory effect, significantly reduces renal toxicity and liver toxicity induced by the anticancer agent cisplatin back so as to be almost normal condition, and significantly inhibits the intestinal crypt loss caused by irradiation, compared with the herbal composition of comparative example. Therefore, the herbal composition with increased fat-soluble polyphenols of the present invention can be effectively used as a composition for cancer treatment, an anti-cancer adjuvant, a composition for enhancing immune function, a composition for protecting a living body, and a composition for preventing side effects of cancer treatment. 1. A method for preparing an herbal composition with increased fat-soluble polyphenols comprising the following steps:{'i': Angelica Radix, Cnidium Rhizoma', 'Paeonia Radix;, '1) preparing an aqueous ethanol extract from the herb mixture composed of , and'}{'i': Angelica Radix, Cnidium Rhizoma', 'Paeonia Radix, '2) preparing a hot-water extract from the herb mixture composed of , and of step 1) above;'}3) mixing a certain portion of the aqueous ethanol extract of step 1) and the hot-water extract of step 2), and then precipitating in 66-83% ethanol to obtain polysaccharides; and4) mixing the other remaining portion of the aqueous ethanol extract of step 1) and the polysaccharides of step 3).2. The method for preparing an herbal composition with increased fat-soluble polyphenols according to ...

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Номер записи: 39
01-05-2014 дата публикации

NOVEL N3S1 CHELATOR-FOLATE DERIVATIVES, PREPARATION METHOD THEREOF AND COMPOSITION FOR DIAGNOSIS OR TREATMENT OF CANCER CONTAINING THE SAME AS AN ACTIVE INGREDIENT

Номер: US20140121361A1
Автор: CHOI Sun Ju, HONG Young-Don, LEE Dong Eun, Lee So-Young, LIM Jae Cheong
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Novel NSchelator-folate derivatives, a preparation method thereof, and a composition for diagnosis and treatment of tumor including the same as an active ingredient are provided. The novel NSchelator-folate derivatives or a pharmaceutically acceptable salt thereof are easily introduced into the cells using receptor binding to tumor expressing α-folate receptor (α-FR). Accordingly, the folate derivatives, labeled with radioisotope such as technetium, or rhenium, can be advantageously used for the diagnosis and treatment of tumor using tumor imaging and irradiation from the isotope, and therefore, can be widely used for the purpose of labeling a variety of radiopharmaceuticals. 7. The preparation method of claim 3 , wherein the solid phase support is Wang resin or Merrifield resin.8. The NSchelator-folate derivative of claim 1 , further labeled with radioisotope.9. The radioisotope-labeled NSchelator-folate derivative of claim 8 , wherein the radioisotope is technetium or rhenium.10. A method for preparation of a radioisotope-labeled complex claim 8 , comprising transchelating the NSchelator-folate derivative of claim 8 , using ligand exchange reaction kit.11. A composition for diagnosis of tumor claim 8 , comprising the radioisotope-labeled NSchelator-folate derivative of as an active ingredient.12. A composition for treatment of tumor claim 8 , comprising the radioisotope-labeled NSchelator-folate derivative of as an active ingredient.13. A kit for radioisotope-labeling the NSchelator-folate derivative of as set forth in . This application claims priority from Korean Patent Application No. 10-2012-0119743, filed on Oct. 26, 2012, in the Korean Intellectual Property Office, the disclosure of which is incorporated herein by reference in its entirety.1. Field of the InventionThe present invention relates to novel NSchelator-folate derivatives, preparation method thereof and composition for diagnosis or treatment of cancer containing the same as an active ingredient.2. ...

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Номер записи: 40
06-02-2020 дата публикации

METHOD FOR DETECTING RADIONUCLIDE, PROCESS FOR DETECTING RADIONUCLIDE USING THE SAME, AND RADIATION DETECTOR FOR THE SAME

Номер: US20200041661A1
Автор: JEON Byoungil, KIM Jong Yul, LEE JOO HYUN, LEE Nam-Ho, LIM Ki Seo, MOON Myung Kook
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

A method for detecting a radionuclide using energy spectrum data represented by a count depending on energy obtained from a radiation detector, including: calculating a count ratio for a particular energy value using a background energy spectrum data measured without a target object to detect the radionuclide and a target energy spectrum measured in the presence of the target object; and comparing a background count ratio and a target object count ratio, where the count ratio is a ratio of a low count sum of count values which is an energy value or less divided by a high count sum of the count values which is greater than the particular energy value, or a ratio of the low count sum of the count values which is smaller than the particular energy value divided by the high count sum of the count values which is the particular energy value or greater. 110-. (canceled)11. A method for detecting a radionuclide using energy spectrum data represented by a count depending on energy obtained from a radiation detector , comprising:respectively calculating a count ratio for a particular energy value using a background energy spectrum data measured without a target object to detect the radionuclide and a target energy spectrum measured in the presence of the target object; andcomparing a background count ratio and a target object count ratio,wherein the count ratio is defined as a ratio of a low count sum of count values which is a particular energy value or less divided by a high count sum of the count values which is greater than the particular energy value, or a ratio of the low count sum of the count values which is smaller than the particular energy value divided by the high count sum of the count values which is the particular energy value or greater.12. The method for detecting the radionuclide as claimed in claim 11 , further comprising:searching the energy value having an identical count ratio by comparing the background count ratio and the target object count ratio.13. ...

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Номер записи: 41
03-03-2022 дата публикации

METHOD OF TREATING RADIOACTIVE WASTE RESIN AND AN EQUIPMENT THEREFOR

Номер: US20220068517A1
Автор: AHN Hong Joo, CHOI Jung Hoon, Kang Hyun Woo, Kim In Tae, LEE Ki Rak, Park Geun Il, PARK Hwan Seo
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present invention relates to a method of separating and removing a radioactive nuclide, particularly, C-14 and tritium from a radioactive waste resin, and an equipment therefor. The method of treating a radioactive waste resin of the present invention includes recycling of condensate water from which a C-14 radionuclide in the condensate water is removed, into a treatment part for a radioactive waste resin.

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Номер записи: 42
25-02-2021 дата публикации

Sparger and nuclear power plant having the same

Номер: US20210057116A1
Автор: Hanok Kang, Jihan CHUN, Kyungjun KANG, Moon Jung
Принадлежит: Korea Atomic Energy Research Institute KAERI

A sparger includes a main pipe connecting inside and outside of a water tank having a storage space therein for storing cooling water, so as to define a flow path through which steam and air containing radioactive materials generated outside the water tank are discharged into the cooling water, a header part connected to one end portion of the main pipe located in the storage space, and having a storage chamber in which the steam and air transferred through the main pipe are collected, and a plurality of discharge nozzles disposed in a spacing manner, each having inlet and outlet formed on one end located in the storage chamber and another end located in the storage space, respectively, to discharge the steam and air from the storage chamber to the storage space, and at least some of the plurality of discharge nozzles protruding from the header part by different lengths.

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Номер записи: 43
29-05-2014 дата публикации

PHARMACEUTICAL COMPOSITION CONTAINING FIBULIN-3 PROTEIN AS AN ACTIVE INGREDIENT FOR INHIBITING THE GROWTH OF CANCER STEM CELLS

Номер: US20140147423A1
Автор: KIM In-Gyu, Kim Kug C., Kim Min J., Kim Seo Y., Lee So Y., Shin Byungchul
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 112-. (canceled)13. A method for inhibiting cancer stem cell growth containing the step of administering a pharmaceutically effective dose of fibulin-3 protein to a subject having cancer stem cells.14. A method for inhibiting cancer stem cell growth containing the step of administering a pharmaceutically effective dose of fibulin-3 over-expressing cell line constructed by transforming fibulin-3 gene or the culture medium of the same to a subject having cancer stem cells.15. The method for inhibiting cancer stem cell growth according to claim 13 , wherein the fibulin-3 protein has the amino acid sequence represented by SEQ. ID. NO: 1.16. The method for inhibiting cancer stem cell growth according to claim 13 , wherein the cancer is lung cancer or breast cancer.1720-. (canceled)21. The method for inhibiting cancer stem cell growth according to claim 13 , wherein the cancer stem cell is selected by the marker selected from the group consisting of those cancer stem cell markers such as CD133 (prominin-1; AC133) claim 13 , CD44 (hyaluronate receptor; P-glycoprotein 1) claim 13 , and ALDH1 (Aldehyde ...

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Номер записи: 44
19-03-2015 дата публикации

Purification method and apparatus for radioactive wastewater containing iodine radionuclides

Номер: US20150076045A1
Автор: Ji Young Lee, Jong Tae Jeong, Kyung Su Kim, Seung Yeop Lee
Принадлежит: Korea Atomic Energy Research Institute KAERI

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.

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Номер записи: 45
05-06-2014 дата публикации

Separation and Recovery Device for Liquid Waste Including Radionuclide, and Separation and Recovery Method Using the Same

Номер: US20140151215A1
Автор: Dong Yong Chung, Hee-Chul Yang, Jeikwon Moon
Принадлежит: Korea Atomic Energy Research Institute KAERI

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.

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Номер записи: 46
05-03-2020 дата публикации

DEVICE FOR MEASURING HEAT TRANSFER RATE

Номер: US20200072683A1
Автор: PARK Hyunsik, RYU Sunguk, YANG Jinhwa, YI Sungjae
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

A device for measuring a heat transfer rate according to the present invention includes: a first layer provided with a first material portion and a second material portion disposed in parallel in a surface direction of an object; a second layer provided with a third material portion disposed in parallel with the first material portion in a thickness direction of the first layer and having the same thermal conductivity as the second material portion, and a fourth material portion disposed in parallel with the second material portion in the thickness direction and having the same thermal conductivity as the first material portion; and a temperature measurement layer to measure a temperature difference in the surface direction between the first layer and the second layer, wherein the temperature measurement layer includes: a thermocouple portion provided with a first contact between the first material portion and the third material portion, and a second contact between the second material portion and the fourth material portion; and a noise detector having a shape corresponding to the thermocouple portion. Accordingly, an amount of electric noise can be detected and removed, thereby improving accuracy. 1. A device for measuring a heat transfer rate , the device comprising:a first layer provided with a first material portion and a second material portion disposed in parallel in a surface direction of an object and having different thermal conductivities;a second layer provided with a third material portion disposed in parallel with the first material portion in a thickness direction of the first layer and having the same thermal conductivity as the second material portion, and a fourth material portion disposed in parallel with the second material portion in the thickness direction and having the same thermal conductivity as the first material portion; anda temperature measurement layer interposed between the first layer and the second layer, and configured to measure a ...

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Номер записи: 47
06-04-2017 дата публикации

IONIC POLYMER MEMBRANE COMPRISING RADIATION-CROSSLINKABLE POLY(VINYL ALCOHOL) AND METHOD OF PREPARATION THEREOF

Номер: US20170098511A1
Автор: HWANG In Tae, Jung Chan Hee, Jung Chang-Hee, SHIN Junhwa, Sohn Joon Yong
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present invention provides an ionic polymer membrane prepared by irradiating the compound represented by formula 1 and an ionic polymer. The ionic polymer membrane of the present invention has the advantage of excellent processability, low production costs, high ion exchange capacity and high durability. Also, the method for preparing the ionic polymer membrane of the invention not only facilitates the production of the ionic polymer membrane in a 3-dimensional network structure which has high ion exchange capacity and high dimensional stability but also makes it easy to produce membranes in various forms and sizes by using the composition itself as a coating solution with using the commercialized inexpensive ionic polymer without additional high-risk multi-step introduction process of ionic exchange group. In the aspect of preparation process, the simplicity of the process and suitable for the mass-production, and the production cost is reduced by saving the processing time as much as minimum 1/15 (56 min.) in comparison to the processing time of the conventional thermal-crosslinking (1 hour). 3. The ionic polymer membrane according to claim 1 , wherein the mixing ratio of the compound represented by formula 1 and the ionic polymer is 1:9 to 8:2.4. The ionic polymer membrane according to claim 1 , wherein the radiation is selected from the group consisting of electron beam claim 1 , gamma-ray claim 1 , and X-ray.5. The ionic polymer membrane according to claim 1 , wherein the total dose of the radiation is 5 kGy-500 kGy.7. The method for preparing an ionic polymer membrane according to claim 6 , wherein the mixed solution includes one or more solvents selected from the group consisting of N-methyl-2-pyrrolidone claim 6 , dimethylsulfoxide claim 6 , and dimethylformamide.8. The method for preparing an ionic polymer membrane according to claim 6 , wherein the spreading is accomplished by one of the methods selected from the group consisting of bar coating claim 6 ...

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Номер записи: 48
23-04-2015 дата публикации

Combustion controller for combustible gas

Номер: US20150108128A1
Автор: Hwan Yeol Kim, Jin Ho Song, Kwang Soon Ha, Yong Mann Song
Принадлежит: Korea Atomic Energy Research Institute KAERI

Provided is a combustion controller for a combustible gas of a pressurized water reactor nuclear power plant, and more particularly, to a combustion controller for a combustible gas installed in a rear end of a filtered vent system outside a containment vessel or an external chimney, configured to convert a combustible gas such as hydrogen, carbon monoxide, or the like, into steam, carbon dioxide, or the like, and simultaneously, operate by itself with no external power supply. Accordingly, the combustion controller for a combustible gas can perform stable combustion control with no probability of explosion of hydrogen through a recombining reaction of the combustible gas, prevent discharge of carbon monoxide, which is a toxic gas, and prevent backward flow of the flame through the quenching mesh.

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Номер записи: 49
12-04-2018 дата публикации

DECONTAMINATION METHOD REDUCING RADIOACTIVE WASTE REMARKABLY AND A KIT THEREFOR

Номер: US20180102194A1
Автор: Choi Mansoo, CHOI Wangkyu, JUNG Chong-Hun, JUNG Jun Young, Kim Seonbyeong, MOON Jeikwon, Park Jungsoon, PARK Sang Yoon, WON Hui-Jun, YOON In-Ho
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present invention provides a decontamination method including the steps of decontaminating an object containing radioactive contaminated metals or alloys with a chemical decontamination agent comprising sulfuric acid (HSO) and forming a Ba or Sr precipitate by adding Ba or Sr cation and hydroxyl ion or halogen anion salts to the decontamination waste water. 1. A decontamination method comprising the following steps:{'sub': 2', '4, 'decontaminating an object containing radioactive contaminated metals or alloys with a chemical decontamination agent comprising sulfuric acid (HSO) (step 1); and'}forming a Ba or Sr precipitate by adding Ba or Sr cation and hydroxyl ion or halogen anion salts to the decontamination waste water generated in step 1 (step 2).2. The decontamination method according to claim 1 , wherein the chemical decontamination agent of step is an oxidative decontamination agent claim 1 , a reductive decontamination agent claim 1 , or a combined decontamination agent thereof.3. The decontamination method according to claim 1 , wherein the decontamination method additionally includes a step of separating the precipitate (step 3).4. The decontamination method according to claim 2 , wherein the oxidative decontamination agent includes an oxidizing agent and a metal ion.5. The decontamination method according to claim 4 , wherein the oxidizing agent is one or more agents selected from the group consisting of KMnO claim 4 , NaMnO claim 4 , HCrO claim 4 , and HMnO.6. The decontamination method according to claim 2 , wherein the reductive decontamination agent includes a reducing agent and a metal ion.7. The decontamination method according to claim 6 , wherein the reducing agent is one or more agents selected from the group consisting of NaBH claim 6 , HS claim 6 , NH claim 6 , and LiAlH.8. The decontamination method according to claim 1 , wherein the object containing radioactive contaminated metals or alloys in step 1 is generated from the inner system of ...

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Номер записи: 50
03-07-2014 дата публикации

URANIUM DIOXIDE NUCLEAR FUEL PELLET HAVING METALLIC MICROCELLS AND FABRICATING METHOD THEREOF

Номер: US20140185731A1
Автор: KIM Dong-Joo, Kim Jong-Hun, KIM Keon-Sik, KOO Yang-Hyun, OH JangSoo, Rhee Young Woo, YANG Jae-Ho
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A uranium dioxide nuclear fuel pellet comprising:microcells defined by micro-partitions comprising a metallic element; anduranium dioxide contained in the microcells such that at least part of fission products would be trapped in the microcells upon fissioning.2. The uranium dioxide nuclear fuel pellet according to claim 1 , wherein the metallic element is Cr.3. The uranium dioxide nuclear fuel pellet according to claim 1 , wherein the metallic element is Mo.4. The uranium dioxide nuclear fuel pellet according to claim 1 , wherein an average size of the microcells is about 30 μm to about 400 μm.5. The uranium dioxide nuclear fuel pellet according to claim 1 , wherein a ratio of the micro-partitions with respect to the uranium dioxide is about 0.1% to about 10.0% by weight.6. The uranium dioxide nuclear fuel pellet according to claim 1 , wherein a single grain of the uranium oxide is filled in each of at least some of the microcells.7. The uranium dioxide nuclear fuel pellet according to claim 1 , wherein one of the micro-partitions is located between two immediately neighboring grains of the uranium oxide and contacts the two immediately neighboring grains of the uranium oxide.8. The uranium dioxide nuclear fuel pellet according to claim 1 , wherein the micro-partitions are configured to inhibit the fission products from passing therethrough.9. The ...

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Номер записи: 51
21-04-2016 дата публикации

Chromium-Aluminum Binary Alloy Having Excellent Corrosion Resistance and Method of Manufacturing Thereof

Номер: US20160108507A1
Автор: Dong Jun Park, Hyun Gil Kim, Il Hyun KIM, Jeong-Yong Park, Jung Hwan Park, Yang-Hyun Koo, Yang-Il Jung
Принадлежит: Korea Atomic Energy Research Institute KAERI

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 1 ) mixing and melting a raw material comprising: 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 (Step 2 ) solution treating the alloy melted in Step 1. The chromium-aluminum binary alloy may be easily produced and has ductility, thus being highly applicable as a coating material for a material requiring high-temperature corrosion resistance and wear resistance.

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Номер записи: 52
29-04-2021 дата публикации

FLUID TRANSFER APPARATUS

Номер: US20210123438A1
Автор: BAIK Minhoon, KOH Yongkwon, KWON Jangsoon, LEE Jaekwang
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The fluid transfer apparatus includes a rotor housing for forming a fluid compression space having the shape of an epitrochoid surface; a rotor eccentrically rotates inside the fluid compression space by being eccentrically coupled to a rotation shaft; and a rotor housing cover covering the fluid compression space of the rotor housing and including a rotation shaft penetration hole formed at the center of the cover, and a first cover fluid channel and second cover fluid channel are symmetrically formed on the opposite sides of each other with the rotation shaft penetration hole in the middle, wherein a plurality of rotor housing covers are arranged to be spaced apart from each other, one rotor housing is arranged between every two rotor housing covers, one rotor is arranged in the fluid compression space of each rotor housing, and each rotor is arranged to face a different direction from a neighboring rotor. 1. A fluid transfer apparatus , comprising:a rotor housing defining a fluid compression space having an epitrochoid surface;a rotor disposed in the fluid compression space of the rotor housing so as to divide the fluid compression space of the rotor housing into a plurality of volume variance spaces, and eccentrically coupled to a rotation shaft rotating in place so as to rotate eccentrically within the fluid compression space; anda rotor housing cover formed to cover the fluid compression space of the rotor housing, and having a rotation shaft penetration hole formed through a center thereof, and a first cover channel and a second cover channel symmetrically formed on opposite sides to each other with respect to the rotation shaft penetration hole,wherein the rotor housing cover is provided in plurality, disposed to be spaced apart from one another,wherein the rotor housing is provided in plurality, each disposed between neighboring rotor housing covers thereof,wherein the rotor is provided in plurality, disposed in the fluid compression spaces of the rotor ...

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Номер записи: 53
09-04-2020 дата публикации

Apparatus for Treating Spent Radioactive Ion Exchange Resins and Method for Treating Spent Radioactive Ion Exchange Resin

Номер: US20200109069A1
Автор: Eun Hee Chul, Kim Hyung Ju, Lee Keun Young, SEO Bum Kyoung, YANG Hee Chul
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present invention relates to an apparatus for treating a spent ion exchange resin, the apparatus including: a graphite reactor for receiving a spent ion exchange resin including a radionuclide-containing ion exchange group therein; a graphite heater for heating the spent ion exchange resin; an inert gas injection tube for injecting an inert gas into the graphite reactor for drying and carbonizing the spent ion exchange resin; and a halogenation gas injection tube for injecting a halogen-containing gas or a halogenation compound gas into the graphite reactor for halogenation of a compound derived from the radionuclide-containing ion exchange group, and to a method for treating a spent ion exchange resin, the method including steps of (A) drying a spent ion exchange resin including a radionuclide-containing ion exchange group; (B) producing a compound derived from the radionuclide-containing ion exchange group by separating the radionuclide-containing ion exchange group from the dried spent ion exchange resin; (C) carbonizing the spent ion exchange resin from which the radionuclide-containing ion exchange group is separated; and (D) converting a compound derived from the radionuclide-containing ion exchange group into a radionuclide-containing halide, in which steps (A) to (D) are performed in the same graphite reactor. 1. An apparatus for treating a spent ion exchange resin , the apparatus comprising: a graphite reactor for receiving a spent ion exchange resin comprising a radionuclide-containing ion exchange group therein;a graphite heater for heating the spent ion exchange resin;an inert gas injection tube for injecting an inert gas into the graphite reactor for drying and carbonizing the spent ion exchange resin; anda halogenation gas injection tube for injecting a halogen-containing gas or a halogenation compound gas into the graphite reactor for halogenation of a compound derived from the radionuclide-containing ion exchange group.2. The apparatus of claim 1 ...

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Номер записи: 54
18-04-2019 дата публикации

CONTINUOUS-TYPE LONG-RANGED MOLTEN METAL LEVEL MEASURING DEVICE AND THERMAL SYSTEM USING MULTI-POINT TEMPERATURE SENSOR

Номер: US20190113378A1
Автор: Eoh Jae Hyuk, JEONG Ji-Young, Kim Byeongyeon, Lee Yong Bum
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

A molten metal level measuring device in a continuous molten metal level measuring device uses temperature compensation. The device includes a cylindrical bobbin, a liquid level measuring unit helically wound around an outer surface of the bobbin, a circular inner cylinder in which the bobbin and the liquid level measuring part are located and which seals the bobbin and the liquid level measuring part from the outside and has the same axial direction as the bobbin, and a cylindrical protective tube in which the inner cylinder is located and which has the same axial direction as the bobbin and has one open end. Thermocouples extend axially in the space between the inner cylinder and the protective tube, and a control unit controls the liquid level measuring part to measure a liquid level of the molten metal based on the temperatures measured by the thermocouples. 1. A molten metal level measuring device in a continuous molten metal level measuring device using temperature compensation , the molten metal level measuring device comprising:a cylindrical bobbin;a liquid level measuring part helically wound around an outer surface of the bobbin;a circular inner cylinder in which the bobbin and the liquid level measuring part are located and which seals the bobbin and the liquid level measuring part from the outside and has the same axial direction as the bobbin;a cylindrical protective tube in which the inner cylinder is located, and which has the same axial direction as the bobbin and has one open end;a plurality of thermocouples disposed extending in the axial direction in the space formed by the outer side of the inner cylinder and the inner side of the protective tube; anda control unit which controls the liquid level measuring part to measure a liquid level of the molten metal and outputs a corrected value of the liquid level measured from the liquid level measuring part on the basis of temperatures respectively measured by the plurality of thermocouples.2. The ...

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Номер записи: 55
13-05-2021 дата публикации

Sensor tube of humidity sensor, tube assembly, and humidity sensor system

Номер: US20210140905A1
Автор: Dong Jin Euh, Hae Seob Choi, Tae Soon Kwon, Woo Shik Kim, Yeon Sik Kim
Принадлежит: Korea Atomic Energy Research Institute KAERI

A sensor tube according to the present disclosure includes a body including a body extension having opposite ends connected to measurement air connection pipes and an opening, the measurement air connecting pipes being connected to a humidity sensor to deliver moisture to the humidity sensor using measurement air or allow the measurement air released from the humidity sensor to flow therethrough, and the opening being formed in the body extension to cause an interior space of the body extension and the outside to be in communication with each other such that the moisture is introduced into the interior space of the body extension from the outside through the opening, and an opening/closing part that selectively opens or closes the opening by being operated by a difference in pressure between the interior space of the body extension and the outside.

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Номер записи: 56
24-07-2014 дата публикации

TWO-FAR END SUPPORTED ACTUATOR MODULE FOR SNAKE ROBOT USING INNER WIRE

Номер: US20140202275A1
Автор: EOM Heung Seop, KIM Chang Hoi, SHIN Hocheol
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A two-far end supported actuator module for a snake robot using an inner wire , comprising: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; anda 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.2. The two-far end supported actuator module ...

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Номер записи: 57
24-07-2014 дата публикации

Nuclear fuel rod for fast reactors including metallic fuel slug coated with protective coating layer and fabrication method thereof

Номер: US20140205054A1
Автор: ByoungOon LEE, Chan Bock Lee, Jin-Sik Cheon, Jong-Hyuk Baek, Jun Hwan Kim, Junehyung KIM, Ki Hwan Kim, Seok-Jin Oh, Seong Woo Yang, Sung-Ho Kim, Yoon-Myeong Woo, Young-Mo Ko
Принадлежит: Korea Atomic Energy Research Institute KAERI, Korea Hydro and Nuclear Power Co Ltd

Provided are a nuclear fuel rod for fast reactors that includes a metallic fuel slug coated with a protective coating layer and a fabrication method thereof. The nuclear fuel rod for fast reactors that includes a surface treated metallic fuel slug and a cladding tube according to the present invention has an excellent effect of stabilizing components of the metallic fuel slug and fission products or impurities, because the interdiffusion between the metallic fuel slug and the cladding tube does not occur. Also, since the uniform coating on the surface of the metallic fuel slug may be facilitated and fabrication costs may be significantly reduced in comparison to a typical technique of using a functional material for preventing the interdiffusion at an inner surface of the cladding tube, it may be suitable for fabricating the nuclear fuel rod for fast reactors.

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Номер записи: 58
14-05-2015 дата публикации

CROSSLINKED SPEEK CATION EXCHANGE MEMBRANE HAVING IMPROVED CHEMICAL STABILITY BY RADIATION AND METHOD OF PREPARING THE SAME

Номер: US20150133570A1
Автор: Lee Sun-Young, SHIN Junhwa, Sohn Joon Yong, SONG Ju-Myung, WOO Hyun-Su
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A method of preparing a crosslinked sulfonated poly(ether ether ketone) (SPEEK) cation exchange membrane , the method comprising:preparing a crosslinker mixture of a first crosslinker containing two vinyl oxy groups and a second crosslinker containing three vinyl groups;preparing a mother liquor containing the crosslinker mixture, a SPEEK polymer substituted with sodium, and a solvent; andcasting the mother liquor and then irradiating radiation thereon.3. The method of claim 1 , wherein in the crosslinker mixture claim 1 , 60 to 95 wt % of the first crosslinker and 5 to 40 wt % of the second crosslinker are mixed with each other.4. The method of claim 1 , wherein the mother liquor contains 0.1 to 20 wt % of the crosslinker mixture claim 1 , 1 to 30 wt % of the SPEEK polymer substituted with sodium claim 1 , and 65 to 95 wt % of the solvent.5. The method of claim 1 , wherein the first crosslinker contains any one or at least two selected from 1 claim 1 ,4-butanediol divinyl ether claim 1 , 1 claim 1 ,6-hexanediol ether claim 1 , di(ethylene glycol)divinyl ether claim 1 , tri(ethylene glycol)divinyl ether claim 1 , tetra(ethylene glycol)divinyl ether claim 1 , and 1 claim 1 ,4-cyclohexanedimethanol divinyl ether.6. The method of claim 1 , wherein the second crosslinker contains any one or a mixture of at least two selected from triallyl isocyanurate and pentaerythritol triallyl ether.7. The method of claim 1 , wherein the solvent is any one or a mixture of at least two selected from a group ...

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Номер записи: 59
11-05-2017 дата публикации

SMART BED FOR RADIATION THERAPY

Номер: US20170128743A1
Автор: BAE Yeonggeol, JEONG Kyungmin, KIM Seungho, NA Hyeonseok
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

A smart bed for a radiation therapy includes a rest to which radiation is applied, a support structure having one end fixed to the ground and having four columns disposed to be spaced apart from one another, centered around the rest, four connection parts extending from one side of each of the columns and connected to each vertex of the rest, and lengthened or shortened through a linear actuator provided on one side thereof, and a controller independently controlling each of the linear actuators to implement movement of the rest, wherein rotational and translational movement of the rest is implemented such that radiation is applied to each position of an upper surface and a lower surface of the rest. 1. A smart bed for a radiation therapy , the smart bed comprising:a rest to which radiation is applied;a support structure having one end fixed to the ground and having four columns disposed to be spaced apart from one another, centered around the rest;four connection parts extending from one side of each of the columns and connected to each vertex of the rest to support the rest, and lengthened or shortened through a linear actuator provided on one side thereof; anda controller independently controlling each of the linear actuators to implement movement of the rest,wherein rotational and translational movement of the rest is implemented such that radiation is applied to each position of an upper surface and a lower surface of the rest.2. The smart bed of claim 1 , wherein the controller selects two certain linear actuators and transmits an operational signal such that the rest is rotated on the basis of an X axis or a Y axis of the rest.3. The smart bed of claim 1 , wherein the controller selects all the linear actuators and transmits an operation signal claim 1 , for a vertical translational movement of the rest.4. The smart bed of claim 1 , wherein each of the connection parts has an actuator fixing fastening member formed to surround the column at one end of the ...

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Номер записи: 60
23-04-2020 дата публикации

Reactor cooling and electric power generation system

Номер: US20200126680A1
Автор: Hyunjun CHO, Joohyung MOON, Juhyeon YOON, Kilsung KWON, Seok Kim, Seungyeob RYU, Soojai SHIN, Youngin Kim
Принадлежит: King Abdullah City for Atomic and Renewable Energy, Korea Atomic Energy Research Institute KAERI

Also, the reactor cooling and power generation system according to the present invention may continuously operate during an accident as well as a normal operation so as to cool the reactor and produce emergency power, thereby improving system reliability. In addition, the reactor cooling and power generation system according to the present invention may facilitate application of safety class or seismic design with a small scale facility, thereby improving the reliability owing to the application of the safety class or seismic design.

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Номер записи: 61
07-08-2014 дата публикации

MULTI STAGE SAFETY INJECTION DEVICE AND PASSIVE SAFETY INJECTION SYSTEM HAVING THE SAME

Номер: US20140219409A1
Автор: BAE Young Min, Kim Keung Koo, Kim Young In, Lee Won Jae, MOON Joo Hyung, Park Cheon Tae, SHIN Soo Jai, YOO Seung Yeop, YOON Ju Hyeon
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A multi stage safety injection device , comprising: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; anda 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.2. The multi stage safety injection device of claim 1 , wherein the safety injection line forms a total flow resistance being increased step by step ...

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Номер записи: 62
14-08-2014 дата публикации

MULTI-JOINT RADIOTHERAPY APPARATUS USING FLEXIBLE AND ROTARY COUPLING WAVEGUIDE PIPE

Номер: US20140225534A1
Автор: Chai JongSeo, Jeong Kyung-min, KIM Seungho, Lee Byeong-No, LEE Byung Cheol, LEE JongChul, LEE SEUNGHYUN, PARK Hyung Dal, Shin SeungWook, Song Ki Baek
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

A radiotherapy apparatus includes a beam irradiation head (), a linear accelerating means () provided at the beam irradiation head (), a robot arm () connected with the beam irradiation head () and having a plurality of joints, a waveguide () built in the robot arm and connected with the linear accelerating means (), and an electromagnetic wave oscillator () disposed outside the robot arm () and generating electromagnetic waves so that the electromagnetic waves are propagated to the linear accelerating means () through the waveguide (). 1. A radiotherapy apparatus comprising:a beam irradiation head;a linear accelerator provided at the beam irradiation head;a robot arm connected with the beam irradiation head and comprising a plurality of joints;a waveguide built in the robot arm and connected with the linear accelerator; andan electromagnetic wave oscillator configured to generate electromagnetic waves for providing the electromagnetic waves to the linear accelerator, wherein the electromagnetic wave oscillator is disposed outside the robot arm such that the robot arm does not carry the weight of the electromagnetic wave oscillator while the electromagnetic waves generated from the electromagnetic wave oscillator propagate to the linear accelerator through the wave guide installed through the robot arm.2. The apparatus according to claim 1 , further comprising a rotary-coupling waveguide pipe provided at one of the plurality of joints of the robot arm such that the electromagnetic waves generated from the electromagnetic wave oscillator propagate to the linear accelerator through the rotary coupling waveguide pipe.3. The apparatus according to claim 1 , further comprising a rotary-coupling waveguide pipe which comprises a body disposed at one of the plurality of joints claim 1 , and a rotary-coupling part which is rotatably coupled at one end of the body.4. The apparatus according to claim 1 , wherein the waveguide has a straight pipe structure or a flexible pipe ...

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Номер записи: 63
04-06-2015 дата публикации

Preparation of Technetium-99M Tricarbonyl Labeled Glycine Monomer or Oligomer Containing Probes That Have Biomolecules and Its Application as Imaging Complex-Composition

Номер: US20150151011A1
Автор: Jang Beom Su, Lee Joo-Sang, PARK Sang Hyun, Rho Jong-Kook
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A method for preparing a technetium-99m-labeled monomer or oligomer , comprising:a) synthesizing a technetium-99m tricarbonyl precursor; andb) labeling a glycine monomer or oligomer with the technetium-99m tricarbonyl precursor.2. The method of claim 1 , wherein the glycine oligomer is a glycine trimer or a glycine pentamer.3. The method of claim 1 , wherein the glycine monomer or oligomer is further conjugated into a targeted peptide.4. The method of claim 3 , wherein the targeted peptide is selected from the group consisting of an RGD peptide (arginylglycylaspartic acid) claim 3 , neurotensin claim 3 , somatostatin claim 3 , angiotensin claim 3 , luteinizing hormone releasing hormone claim 3 , insulin claim 3 , oxytocin claim 3 , neurokinin-1 claim 3 , vasoactive intestinal peptide claim 3 , substance P claim 3 , neuropeptide Y claim 3 , endothelin A claim 3 , endothelin B claim 3 , bradykinin claim 3 , interleukin-1 claim 3 , epidermal growth factor claim 3 , cholecystokinin claim 3 , galanin claim 3 , melanocyte-stimulating hormones claim 3 , lanreotide claim 3 , octreotide claim 3 , and arginine-vasopressin. The present invention relates to a method for preparing a technetium-99m tricarbonyl-labeled glycine monomer or oligomer in a single process using automated peptide synthesis, and an imaging contrast composition containing the technetium-99m tricarbonyl-labeled glycine ...

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Номер записи: 64
14-08-2014 дата публикации

MULTI STAGE SAFETY INJECTION DEVICE AND PASSIVE SAFETY INJECTION SYSTEM HAVING THE SAME

Номер: US20140226778A1
Автор: BAE Young Min, KANG Han Ok, Kim Keung Koo, KIM Tae Wan, Kim Young In, LEE Jun, Lee Won Jae, MOON Joo Hyung, Park Cheon Tae, PARK Keun Bae, SHIN Soo Jai, YOO Seung Yeop, YOON Ju Hyeon
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present disclosure may disclose a multi stage safety injection device and a passive safety injection system having the same, 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 state between the reactor vessel and the safety injection tank, a safety injection line connected to a lower end portion of 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 a flow control line extended from the safety injection line to an inner portion of the safety injection tank, and provided with safety injection ports into which coolant is injected at predetermined heights, respectively, to reduce the 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. 1. A multi stage safety injection device , comprising: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 state between the reactor vessel and the safety injection tank;a safety injection line connected to a lower end portion of 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; anda flow control line extended from the safety injection line to an inner portion of the safety injection tank, and ...

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Номер записи: 65
10-06-2021 дата публикации

PASSIVE INFINITE COOLING STRUCTURE FOR NUCLEAR REACTOR AND METHOD OF OPERATING THE SAME

Номер: US20210174977A1
Автор: Park Hyun Sik, Yi Sung-Jae
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present invention relates to a passive infinite cooling system for a nuclear reactor and a method of operating the same. The system includes an energy release space in which a reactor vessel is accommodated, an energy absorbing space separated from the energy release space, an energy transfer space, which is provided above the energy absorbing space, absorbs and cools heat transferred from the reactor vessel, and discharges the absorbed heat to the outside through an outer wall thereof, a first cooling flow path through which the heat in the reactor vessel is transferred to the energy transfer space, a pressure balance pipe through which the pressure in the energy release space is transferred to the energy absorbing space, and a coolant spray pipe through which the cooling water in the energy absorbing space pressurized by the pressure balance pipe is transferred to the energy transfer space. The energy transfer space includes a saturated vapor pressure cooling chamber, which is formed to be connected to an inner side of an upper outer wall of the cooling space, and in which cooling water is accommodated, a heat exchanger of the first cooling flow path is located, and a spray-side end of the coolant spray pipe is located, and a reference atmospheric pressure chamber, which is provided below the saturated vapor pressure cooling chamber and communicates with the saturated vapor pressure cooling chamber, is filled with air so as to achieve a pressure balance with the cooling water in the saturated vapor pressure cooling chamber, and in which a water level thereof varies according to a pressure in the saturated vapor pressure cooling chamber. 1. A passive infinite cooling system for a nuclear reactor , the system comprising:an energy release space within which is a reactor vessel, in which a reactor core is accommodated;an energy absorbing space in which cooling water is accommodated while being separated from the energy release space and to which a pressure in the ...

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Номер записи: 66
25-05-2017 дата публикации

PASSIVE HEAT REMOVAL SYSTEM AND NUCLEAR POWER PLANT INCLUDING SAME

Номер: US20170148533A1
Автор: BAE Young Min, HA Jae Joo, Han Hun Sik, JUNG SEO YOON, KANG Han Ok, KANG Kyung Jun, Kim Keung Koo, KIM Tae Wan, Kim Young In, Kim Young Soo, MOON Joo Hyung, Park Cheon Tae, RYU Seung Yeob, SHIN Soo Jai, YOON Ju Hyeon
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present invention relates to a passive heat removal system which circulates cooling fluid via a main water supply line, connected to the lower inlet of a steam generator, and a main steam pipe, connected to the top outlet of the steam generator, to the steam generator, in order to remove sensible heat of a reactor coolant system and residual heat of a core, the passive heat removal system comprising: supplementary equipment for receiving surplus cooling fluid or supplying supplementary cooling fluid in order to maintain the flow rate of the cooling fluid within a predetermined range, wherein the supplementary equipment comprises: a supplementary tank, installed at a predetermined height between the lower inlet and the top outlet of the steam generator, for receiving the surplus cooling fluid or supplying the supplementary cooling fluid, passively, depending on the flow rate of the cooling fluid; a first connection pipe, connected to the main steam pipe and the supplementary tank, for forming a flow path to allow the cooling fluid, exhausted to the main steam pipe from the steam generator, to flow to the supplementary tank; and a second connection pipe connected to the supplementary tank and the main water supply pipe for forming a supply flow path of the supplementary cooling fluid supplied from the supplementary tank. 1. A passive residual heat removal system for circulating cooling fluid to a steam generator through a main feedwater line connected to a lower inlet of the steam generator and a main steam line connected to an upper outlet of the steam generator to remove sensible heat in a reactor coolant system and residual heat in a core during an accident , the passive residual heat removal system comprising:a makeup facility configured to accommodate excess cooling fluid or supply makeup cooling fluid to maintain an amount of the cooling fluid within a preset range,wherein the makeup facility comprises:a makeup tank provided at a preset height between a ...

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Номер записи: 67
25-05-2017 дата публикации

METHOD FOR TREATMENT OF SPENT RADIOACTIVE ION EXCHANGE RESINS, AND THE APPARATUS THEREOF

Номер: US20170148535A1
Автор: BAIK Min-Hoon, CHOI Jong-Won, CHUNG Dong Yong, Kim Hyung-Ju, YANG Hee-Chul
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

A method and an apparatus for the treatment of waste ion exchange resins containing radionuclides, and the present invention relates to a method for the treatment of waste ion exchange resins containing radionuclides by the stepwise heat treatment and an apparatus to accomplish the said method. 1. A method for treating waste ion exchange resins containing radionuclides comprising the following steps:drying waste ion exchange resins containing radionuclides (step 1);separating the ion exchanger containing radionuclides from the dried waste ion exchange resin (step 2);converting the volatile compound containing radionuclides obtained from the ion exchanger separated above into non-volatile sulfur oxides containing radionuclides (step 3);converting the sulfur oxides containing radionuclides above into chlorides containing radionuclides (step 4); andseparating and collecting radionuclides from the chlorides containing radionuclides above by volatilization and condensation (step 5).2. The method for treating waste ion exchange resins containing radionuclides according to claim 1 , wherein the method additionally comprises a step of forming carbides from the remaining organic material generated in the waste ion exchange resin whose ion exchanger was separated in step 2.3. The method for treating waste ion exchange resins containing radionuclides according to claim 2 , wherein the formation of carbides is performed at 550˜700° C.4. The method for treating waste ion exchange resins containing radionuclides according to claim 1 , wherein the drying in step 1 is performed at 100˜150° C.5. The method for treating waste ion exchange resins containing radionuclides according to claim 1 , wherein the separation of ion exchanger in step 2 is performed at 150˜400° C.6. The method for treating waste ion exchange resins containing radionuclides according to claim 1 , wherein the conversion into sulfur oxides containing radionuclides in step 3 is performed at 400˜550° C.7. The method ...

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Номер записи: 68
15-09-2022 дата публикации

METHOD AND APPARATUS FOR TRAINING NUCLIDE IDENTIFICATION MODEL

Номер: US20220291399A1
Автор: Kim Chang Hwoi, KIM Hyeonmin, KWON Inyoung, OH Jin Suk, SHIN Dongseong
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

A method for training an apparatus for training a nuclide identification model is provided. In the method, nuclide data is classified into characteristics of energy spectrums for nuclides, training data is generated based on a number of data in each of the classified characteristics, and the nuclide identification model is trained by using the training data. 1. A method for training an apparatus for training a nuclide identification model , the method comprising:classifying nuclide data into characteristics of energy spectrums for nuclides;generating training data based on a number of data in each of the classified characteristics; andtraining the nuclide identification model by using the training data.2. The method of claim 1 , wherein the classifying the nuclide data into the characteristics of the energy spectrums for the nuclides comprises:preparing, as raw data for a complex nuclide, background data, single nuclide radiation measurement data, and complex nuclide radiation measurement data; andsorting the raw data into the characteristics of the energy spectrums for the nuclides, the characteristics of the energy spectrums for the nuclides being characteristics of energy peaks for the nuclides.3. The method of claim 2 , wherein the sorting the raw data into the characteristics of the energy spectrums for the nuclides includes sorting the raw data into the characteristics of the energy peaks for the nuclides based on one or more sections including at least one of back scatter claim 2 , photo peak claim 2 , and Compton edge.4. The method of claim 3 , wherein the training data includes the number of radiation measurement data for each of the one or more sections.5. An apparatus for training a nuclide identification model claim 3 , the apparatus comprising:an input unit configured to receive nuclide data;a processing unit configured to process the nuclide data; anda model unit comprising a nuclide identification model,wherein the processing unit is configured ...

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Номер записи: 69
21-08-2014 дата публикации

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

Номер: US20140234326A1
Автор: Choi Soo Im, KIM In-Gyu, Shin Byung-Chul
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 113-. (canceled)14. A method for screening an anticancer drug or an enhancer candidate to increase radiosensitivity of non-small cell lung cancer adenocarcinoma cells or non-adenocarcinoma non-small cell lung cancer cells , comprising the following steps:1) treating test materials to the cell line expressing TM4SF4 protein;2) measuring the expression or activity of TM4SF4 protein in the above cell line; and3) selecting the test material demonstrating lower or higher expression or activity of TM4SF4 protein than that of the control non-treated with the test material.15. (canceled)16. The method for screening an anticancer drug or an enhancer candidate according to claim 14 , wherein the expression of TM4SF4 protein in step 2) is measured by one of the methods selected from the group consisting of immunoprecipitation claim 14 , RIA claim 14 , ELISA claim 14 , immunohistochemistry claim 14 , RT-PCR claim 14 , Western blotting claim 14 , and FACS.17. The method for screening an anticancer drug or an enhancer candidate according to claim 14 , wherein the activity of TM4SF4 protein in step 2) ...

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Номер записи: 70
07-05-2020 дата публикации

Method for Treating Radioactive Liquid Waste

Номер: US20200143952A1
Автор: HWANG In Tae, Jeong Kyung Hoon, Jeun Joon Pyo, KIM Dong Woo, Kim Tak Hyun, Lee Kang, Lim Seung Joo, Sohn Joon Yong
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present invention relates to a technology for treating radioactive liquid waste containing a hardly degradable compound, and more specifically, to a technology for treating radioactive liquid waste containing a material such as an organic decontamination agent, an inorganic decontamination agent, liquid scintillation counter liquid waste, and the like generated at nuclear power plants, nuclear facilities, facilities at which radiation (radioactivity) is used, and the like. The method for treating radioactive liquid waste of the present invention includes adding two or more selected from the group consisting of a metal ion, an oxidizing agent, air, oxygen, or nitrous oxide, and a semiconductor to radioactive liquid waste to prepare a pre-treatment solution, and irradiating the pre-treatment solution with radiation. 1. A method for treating radioactive liquid waste the method comprising:adding two or more selected from the group consisting of a metal ion, an oxidizing agent, oxygen or nitrous oxide, air, and a semiconductor to radioactive liquid waste, or adding one or more selected from the group consisting of an oxidizing agent, oxygen or nitrous oxide, air, and a semiconductor to radioactive liquid waste containing a metal ion to prepare a pre-treatment solution; andirradiating the pre-treatment solution with radiation.2. The method of claim 1 , wherein the metal ion is a transition metal ion.3. The method of claim 2 , wherein the transition ion comprises one or more selected from the group consisting of a scandium ion claim 2 , a titanium ion claim 2 , a vanadium ion claim 2 , a chromium ion claim 2 , a manganese ion claim 2 , an iron ion claim 2 , a cobalt ion claim 2 , a nickel ion claim 2 , a copper ion claim 2 , a zinc ion claim 2 , a yttrium ion claim 2 , a zirconium ion claim 2 , a niobium ion claim 2 , a molybdenum ion claim 2 , a technetium ion claim 2 , a ruthenium ion claim 2 , a rhodium ion claim 2 , a palladium ion claim 2 , a silver ion claim 2 , ...

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Номер записи: 71
24-06-2021 дата публикации

ULTRAFAST ELECTRON DIFFRACTION APPARATUS

Номер: US20210193429A1
Автор: BAEK Inhyung, Jang Kyuha, JEONG Young Uk, KIM Hyun Woo, Lee Ki Tae, Vinokurov Nikolay
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

There is provided an ultrafast electron diffraction apparatus including: a photoelectron gun configured to emit an electron beam; a bending portion for emitting the electron beam emitted from the photoelectron gun by changing a travel direction of the electron beam by a predetermined angle; and a sample portion including a sample to be analyzed by the electron beam emitted from the bending portion. The electron beam reaches the sample portion in a state that a pulse of the electron beam is compressed and the timing jitter between the pumping light and probe electron pulse is completely reduced as the travel direction of the electron beam is changed by the predetermined angle through the bending portion. 1. An ultrafast electron diffraction apparatus comprising:a photoelectron gun configured to emit an electron beam;a bending portion for bending the electron beam emitted from the photoelectron gun by changing a travel direction of the electron beam by a predetermined angle; anda sample portion including a sample to be analyzed by the electron beam emitted from the bending portion,wherein the electron beam reaches the sample portion in a state that a pulse of the electron beam is compressed as the travel direction of the electron beam is changed by the predetermined angle through the bending portion.2. The ultrafast electron diffraction apparatus of claim 1 , wherein the bending portion comprises a main bending portion and a plurality of auxiliary bending portions claim 1 , andthe electron beams passing through the main bending portion and emitted through the respective auxiliary bending portions have travel directions of different angles.3. The ultrafast electron diffraction apparatus of claim 1 , wherein the bending portion comprises a main bending portion and a plurality of auxiliary bending portions claim 1 , andthe plurality of auxiliary bending portions are disposed to move the electron beam along different paths.4. The ultrafast electron diffraction apparatus ...

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Номер записи: 72
15-06-2017 дата публикации

CUTTING PROCESS SIMULATION METHOD AND SYSTEM THEREOF

Номер: US20170169158A1
Автор: CHOI Byung Seon, HYUN Dong Jun, JEONG Kwan Seong, KIM GEUN HO, KIM Ik June, LEE Jong Hwan, MOON Jei Kwon
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present invention relates to a cutting process simulation method and a system thereof which can efficiently optimize the decommissioning process of a nuclear facility, thereby saving costs and time and ensuring safety in the decommissioning process. The cutting process simulation system, according to one embodiment of the present invention, may comprise: a display unit: and a control unit which cuts a cutting target in a nuclear facility by using a design program, displays the cut shape on the display unit, and predicts the amount of secondary waste generated in the process of cutting the cutting target. 1. A cutting process simulation system comprising:a display that displays a product; anda controller that cuts a product corresponding to a facility in a nuclear plant by using a design program and that represents a cut geometry on the display.2. The cutting process simulation system of claim 1 , wherein the controller estimates the amount of secondary waste generated from the process of cutting the product.3. The cutting process simulation system of claim 1 , wherein the design program is a CAD (computer-aided design) program.4. The cutting process simulation system of claim 3 , wherein the product is cut by using the CAD program and API (application programming interface) functions.5. The cutting process simulation system of claim 4 , wherein the controller models a cut geometry for cutting the product as a solid by using cutting tools and a cutting trajectory claim 4 , and represents a cut geometry with a thickness and depth on the display by performing a remove operation on the product according to the model of the cut geometry.6. The cutting process simulation system of claim 4 , wherein the controller represents cases where the product is cut claim 4 , where the product is cut but cannot be cut claim 4 , where the product is cut into two parts claim 4 , and where the product is cut into three or more parts.7. The cutting process simulation system of claim ...

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Номер записи: 73
23-06-2016 дата публикации

Beta voltaic battery and method of preparing the same

Номер: US20160180980A1
Автор: Byoung-Gun Choi, Kwang Jae Son, Kyung-Hwan Park, Sung-Weon Kang, Young Rang Uhm
Принадлежит: Electronics and Telecommunications Research Institute ETRI, Korea Atomic Energy Research Institute KAERI

Provided is a beta voltaic battery including a first semiconductor layer, a second semiconductor layer, and a beta-ray generator which is disposed between the first semiconductor layer and the second semiconductor layer and includes a metal substrate having both sides coated with a radioisotope layer. The beta voltaic battery according to the present invention has no sealing layer, but may efficiently shield beta rays through a sandwich structure. Since the sealing layer is absent, the absorption of beta rays by the semiconductor may be improved, and excellent energy conversion efficiency may be obtained because output is improved due to the two semiconductor layers and the radioisotope ray source coated on the both sides.

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Номер записи: 74
02-07-2015 дата публикации

Film target for laser-induced particle acceleration and method of manufacturing the same

Номер: US20150187532A1
Автор: Byung Heon Han, Ha-Na Kim, Kitae Lee, Kyu-Ha Jang, Kyung Nam Kim, Seong Hee PARK, Young Uk Jeong
Принадлежит: Korea Atomic Energy Research Institute KAERI

A film target for laser-induced particle acceleration includes a first target layer on which a laser is incident; an intermediate layer located behind the first target layer along a propagating direction of the laser, and in which an intended ion beam is generated; and a second target layer located opposite to the first target layer with the intermediate layer interposed therebetween.

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Номер записи: 75
08-07-2021 дата публикации

Underwater radiation monitoring system and method

Номер: US20210208288A1
Автор: Jang Guen PARK, Jin Ho MOON, Sung Hee Jung
Принадлежит: Korea Atomic Energy Research Institute KAERI

Provided are an underwater radiation monitoring system and method. The monitoring system includes a plurality of sensors configured to measure a value of underwater radiation in a measurement area in which underwater radiation is to be measured, the plurality of sensors being installed in the measurement area by being arranged in a form which is set on the basis of information about the measurement area; and an electronic device configured to identify a value of underwater radiation in the measurement area on the basis of the values of underwater radiation measured by the plurality of sensors, wherein at least one first sensor among the plurality of sensors is connected to the electronic device to collect measured values obtained from the at least one first sensor and a plurality of second sensors excluding the at least one first sensor and to transmit the collected measured values to the electronic device.

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Номер записи: 76
08-07-2021 дата публикации

LONG-TERM COOLING SYSTEM IN NUCLEAR PLANT AND METHOD USING THE SAME

Номер: US20210210227A1
Автор: CHUN Jihan, JUNG Moon, KANG Hanok, KANG Kyungjun
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

A long-term cooling system in a nuclear power plant according to the present disclosure may include a boundary section disposed inside a containment to enclose a reactor coolant system, and configured to restrict steam containing radioactive materials generated in the reactor coolant system from leaking into paths other than a discharge part, an In-Containment Water Storage Tank (IRWST) disposed outside the boundary section and configured to store refueling water therein, an emergency cooling tank disposed outside the containment and provided with a condensation heat exchanger, a gas-liquid separator connected to the emergency cooling tank outside the containment, and a return line configured to connect the gas-liquid separator and the boundary section such that condensate generated by condensing the steam within the boundary section through the emergency cooling tank and the gas-liquid separator is discharged toward the boundary section upon an occurrence of a nuclear power plant accident. 1. A long-term cooling system in a nuclear power plant , the system comprising:a boundary section disposed inside a containment to enclose a reactor coolant system, and configured to restrict steam containing radioactive materials generated in the reactor coolant system from leaking into paths other than a discharge part;an In-Containment Refueling Water Storage Tank (IRWST) disposed outside the boundary section and configured to store refueling water therein;an emergency cooling tank disposed outside the containment and provided with a condensation heat exchanger;a gas-liquid separator disposed outside the containment and connected to the emergency cooling tank; anda return line configured to connect the gas-liquid separator and the boundary section such that condensate is discharged toward the boundary section upon an occurrence of a nuclear power plant accident, the condensate being generated by condensing the steam of the boundary section through the emergency cooling tank ...

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Номер записи: 77
14-07-2016 дата публикации

PHARMACEUTICAL COMPOSITION COMPRISING SILKWORM AS AN ACTIVE INGREDIENT FOR PREVENTION AND TREATMENT OF TISSUE INJURY BY RADIATION

Номер: US20160199420A1
Автор: Jang Beom Su, Nam YouRee, PARK Sang Hyun
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present invention relates to a pharmaceutical composition for the prevention and treatment of tissue injury caused by irradiation which comprises silkworm hemolymph as an active ingredient. Particularly, when the silkworm hemolymph of the present invention was administered to an animal model with liver damage induced by irradiation, plasma AST and liver MDA were significantly decreased, indicating that the silkworm hemolymph of the invention can be effectively used as a composition for the prevention and treatment of disease caused by the exposure on radiation including tissue injury caused by irradiation, etc. 1. A method for the treatment of tissue injury caused by irradiation containing the step of administering a pharmaceutically effective dose of silkworm hemolymph to a subject with tissue injury caused by irradiation.2. The method for the treatment of tissue injury caused by irradiation according to claim 1 , wherein the radiation comprises gamma ray claim 1 , electron beam claim 1 , UV claim 1 , or X ray.3. The method for the treatment of tissue injury caused by irradiation according to claim 1 , wherein the tissue is liver tissue claim 1 , skin tissue claim 1 , gastro-intestinal tract tissue claim 1 , or respiratory system tissue. This is a continuation of PCT Application No. PCT/KR2014/006613, filed on Jul. 21, 2014, which is incorporated by reference, and which claims priority to Korean Application No. 10-2013-0120099, filed on Oct. 8, 2013.The present invention relates to a pharmaceutical composition comprising silkworm (L.) hemolymph as an active ingredient for the prevention and treatment of tissue injury caused by irradiation.Silkworm (L.) is a larva belonging to Bombycidae which was first recorded in . Silkworm powder has been widely used for diabetics in folk remedy. It was confirmed by animal test and clinical test that silkworm powder had the activity of lowering blood sugar by inhibiting the activity of intestinal α- ...

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Номер записи: 78
20-06-2019 дата публикации

Device for Generating Linearly Polarized Ultra-Short Terahertz Wave

Номер: US20190190223A1
Автор: GUDKOV Boris, Jang Kyuha, JEONG Young Uk, JO Jeong Sang, Lee Ki Tae, PARK Seong Hee, Vinokurov Nikolay
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Provided is a linearly polarized ultra-short terahertz wave generating device which has a parabolic barrel mirror installed at one side of a multiple thin film, to generate an ultra-short terahertz wave having single linear-polarized light and uniformly formed output distribution. 1. A device for generating a linearly polarized ultra-short terahertz wave , comprising:a parabolic mirror barrel configured to extend in one direction, and having a parabolic mirror concaved on an upper surface thereof, with an end surface of the parabolic mirror perpendicular to the extending direction forming a parabola;a plurality of thin films configured to be arranged on the parabolic mirror in the extending direction of the parabolic mirror barrel and having at least some areas thereof disposed to overlap each other; andan electron accelerator configured to generate an electron beam passing through the plurality of thin films,wherein spacing spaces are formed between some areas in which the plurality of thin films overlap each other, and when the electron beam passes through the plurality of thin films and the spacing spaces, an ultra-short terahertz wave is generated between the spacing spaces.2. The device for generating a linearly polarized ultra-short terahertz wave of claim 1 , wherein when the electron beam passes through the thin films claim 1 , the electron beam is formed so that the ultra-short terahertz wave is radially wave-guided in a direction perpendicular to the extending direction in the spacing space.3. The device for generating a linearly polarized ultra-short terahertz wave of claim 2 , wherein a traveling path of the electron beam is formed to meet a central line of the parabola formed by the end surface of the parabolic mirror.4. The device for generating a linearly polarized ultra-short terahertz wave of claim 3 , wherein the terahertz wave traveled downward from a position through which the electron beam passes is reflected on the parabolic mirror to be ...

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Номер записи: 79
22-07-2021 дата публикации

HEAT TRANSFERRING DEVICE WITH PUMPING STRUCTURE

Номер: US20210225535A1
Автор: CHOI Ki Yong, Park Hyun Sik, RYU Sung Uk, Yi Sung-Jae
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

A heat transferring device includes a pumping structure, and more specifically, a heat transferring device having a pumping structure, in which a working fluid of a cooling part is movable in an upward direction without a separate power source, and capable of using gravity while recovering the working fluid, and applying various heat sources to a heating part. To this end, a heat transferring device includes a heating part configured to heat a liquid working fluid and change the liquid working fluid to a gas state, a cooling part configured to cool the gaseous working fluid supplied from the heating part and change the gaseous working fluid to a liquid state, a pressurizing part configured to allow the heating part and the cooling part to communicate with each other so that the gaseous working fluid pressurizes the liquid working fluid, and a recovery part configured to move the liquid working fluid supplied from the cooling part to the heating part. 1. A heat transferring device comprising:a heater configured to heat a liquid working fluid and change the liquid working fluid to a gas state;a cooler configured to cool the gaseous working fluid supplied from the heater and change the gaseous working fluid to a liquid state;a pressurizer configured to allow the heater and the cooler to communicate with each other so that the gaseous working fluid pressurizes the liquid working fluid; anda recoverer configured to move the liquid working fluid supplied from the cooler to the heater.2. The heat transferring device of claim 1 , wherein a pressurizing path is provided in the pressurizer so that the gaseous working fluid pressurizes the liquid working fluid while moving in a downward direction.3. The heat transferring device of claim 2 , wherein a cooling path is provided in the cooler so that the liquid working fluid moves in an upward direction.4. The heat transferring device of claim 3 , wherein a recovery path is provided in the recoverer so that the liquid working ...

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Номер записи: 80
12-07-2018 дата публикации

RADIATION DETECTOR AND METHOD FOR MANUFACTURING SAME

Номер: US20180196147A1
Автор: HA Jangho, JEONG Manhee, KANG Changgoo, KIM Hansoo, Kim Youngsoo, Oh Joonho
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present invention provides a radiation detector comprising: a scintillator for absorbing radiation to generate light; and a light detector formed in the scintillator, wherein the scintillator is composed of a two-dimensional nanomaterial for imparting ductility. The scintillator is formed by laminating the two-dimensional nanomaterial, the two-dimensional nanomaterial being at least one of graphene oxide, reduced graphene oxide, and graphene quantum dots. 1. A radiator detector , comprising:a scintillator for absorbing radiation to generate light; anda light detector formed in the scintillator,wherein the scintillator is formed of a two-dimensional nanomaterial for providing ductility.2. The radiation detector of claim 1 , wherein the scintillator is formed by laminating the two-dimensional nanomaterial which is at least one of a graphene oxide claim 1 , a reduced graphene oxide claim 1 , and graphene quantum dots.3. The radiation detector of claim 1 , wherein the two-dimensional nanomaterial has a chemical formula of MX claim 1 ,wherein the ‘M’ is one of elements which belong to groups 4˜6 in a periodic table, andwherein the ‘X’ is one of S, Se and Te.4. The radiation detector of claim 1 , wherein the light detector includes:a first contact electrode and a second contact electrode disposed on positions spaced apart from each other; andan activation layer for connecting the first contact electrode and the second contact electrode with each other, and for forming an electron-hole pair by absorbing light,wherein the activation layer is formed of a two-dimensional nanomaterial for providing ductility, so as to be coupled to the scintillator in a corresponding shape.5. The radiation detector of claim 4 , wherein the two-dimensional nanomaterial includes at least one of graphene claim 4 , a graphene oxide claim 4 , a reduced graphene oxide claim 4 , and graphene quantum dots.6. The radiation detector of claim 4 , wherein the two-dimensional nanomaterial has a ...

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Номер записи: 81
09-10-2014 дата публикации

Method and Apparatus for Separating Carbon and Oxygen Isotopes by Using Optical Fiber Laser

Номер: US20140301938A1
Автор: Cha Yong-Ho, Chung Dong-Yong, Jeong Do-Young, Park Hyoun-Min
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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) and water (HO) having a carbon or oxygen isotope enriched therein, and cooling the HO to recover COhaving a carbon isotope enriched therein or HO having an oxygen isotope enriched therein. 1. A method of separating a carbon isotope , the method comprising:performing a photolysis process on formaldehyde, including a carbon isotope, by irradiation thereof with ultraviolet light having a wavelength ranging from 340 nm to 360 nm to generate carbon monoxide having a carbon isotope enriched therein and hydrogen;{'sub': 2', '2, 'performing a catalytic oxidation reaction on the carbon monoxide having a carbon isotope enriched therein and the hydrogen to synthesize carbon dioxide (CO) having a carbon isotope enriched therein and water (HO); and'}{'sub': 2', '2, 'cooling the HO to recover COhaving a carbon isotope enriched therein.'}2. The method of claim 1 , wherein the photolysis is performed by irradiation with a third harmonic generated by an optical fiber laser.3. The method of claim 1 , wherein claim 1 , after infrared light having a wavelength ranging from 1020 nm to 1080 nm is pulse modulated and amplified by an optical fiber amplifier claim 1 , ultraviolet light having a wavelength ranging from 340 nm to 360 nm is formed by converting the infrared light into a third harmonic.4. The method of claim 1 , after the performing of the photolysis claim 1 , further comprising:performing formaldehyde synthesis for synthesizing ...

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Номер записи: 82
26-07-2018 дата публикации

APPARATUS AND METHOD FOR SIMULATION OF DISMANTLING OPERATION OF NUCLEAR FACILITY

Номер: US20180210979A1
Автор: CHOI Byungseon, HYUN Dongjun, JEONG Kwanseong, KIM Geunho, KIM Ikjune, LEE Jonghwan, MOON Jeikwon
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present invention relates to a simulation of a nuclear facility dismantling operation, comprising: a database which includes information on at least one task constituting a nuclear facility dismantling operation and information on a virtual space related to the simulation of the dismantling operation; a plurality of head mounted displays (HMDs) which receives inputs of users related to the simulation; a simulation unit which generates the virtual space, transmits to the plurality of HMDs, the image of the virtual space including operator objects corresponding to each of the users of the plurality of HMDs, and processes the simulation of the dismantling operation according to the inputs received from each HMD user, wherein, when simulations which are different in at least one of the number of the users and the progress order of the tasks are processed, the simulation unit compares the simulations on the basis of at least one of the number of the users or the progress order of the tasks and displays a comparison result. 1. A simulation apparatus comprising:a database including information on at least one task constituting a nuclear facility decommissioning operation and information regarding a virtual space related to the simulation of the decommissioning operation;a plurality of head mounted displays (HMDs) receiving inputs from users related to the simulation and outputting an image of the virtual space related to the simulation; anda simulation unit generating the virtual space, transmitting, to the plurality of HMDs, an image of the virtual space including operator objects respectively corresponding to the users of the plurality of HMDs, and performing the simulation of the decommissioning operation according to inputs received respectively from the HMD users,wherein, when simulations which are different in at least one of the number of the users and a progress order of the tasks are performed, the simulation unit compares at least one of measurement values ...

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Номер записи: 83
13-08-2015 дата публикации

Novel Rotenone Derivatives and a Use Thereof

Номер: US20150225416A1
Автор: Byung Yeoup Chung, Chul Hong Park, Hyoungwoo BAI, Seung Sik LEE, Sungbeom LEE, Tae Hoon Kim
Принадлежит: Korea Atomic Energy Research Institute KAERI

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: (In formula 1, R 1 and R 2 are as defined in this description).

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Номер записи: 84
02-07-2020 дата публикации

COMPOSITION FOR PLANT DISEASE CONTROL COMPRISING LIMONENE DERIVATIVES AS ACTIVE INGREDIENTS

Номер: US20200205407A1
Автор: Bai Hyoungwoo, Chung Byung Yeoup, Jung Kwangwoo, Kim Jin-hong, Lee Gun Woong, Lee Seungsik, Lee Sungbeom, Park Yong-Dae
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present invention relates to a composition for controlling plant diseases containing a limonene derivative as an active ingredient. In the present invention, the limonene derivatives have an effect of inhibiting the growth of pv. (Xoo), which is a pathogen mediating bacterial leaf blight, and , which is a pathogen mediating rice blast, and it was confirmed in an experiment with respect to inhibition using volatility (i.e., in a state not being in direct contact with Xoo or ) that the limonene derivatives have a growth inhibitory effect. Accordingly, the limonene derivatives have an inhibitory effect against the growth of Xoo and thus they can be effectively used as a composition for controlling plant diseases. 2. The composition as set forth in claim 1 , wherein the plant disease is rice bacterial leaf blight or rice blast.3Xanthomonas oryzaeOryzae. The composition as set forth in claim 2 , wherein the rice bacterial leaf blight is caused by pv. (Xoo).4Magnaporthe oryzae.. The composition as set forth in claim 2 , wherein the rice blast is induced by5. A method for controlling a plant disease claim 1 , comprising treating a plant infected with plant pathogens with the composition as set forth in .6. The method as set forth in claim 5 , wherein the treatment is to directly spray the composition to a plant or indirectly spray the composition to a plant by volatilization.7. The method as set forth in claim 6 , wherein the plant disease is rice bacterial leaf blight or rice blast.8Xanthomonas oryzaeOryzae. The method as set forth in claim 7 , wherein the rice bacterial leaf blight is caused by pv. (Xoo).9Magnaporthe oryzae.. The method as set forth in claim 7 , wherein the rice blast is caused by10. A fertilizer comprising the composition as set forth in .11. A pesticide formulation comprising the composition as set forth in . The present disclosure relates to a composition for controlling plant diseases using a limonene derivative.Rice is a plant of the class ...

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Номер записи: 85
11-07-2019 дата публикации

Magnetic Cesium Adsorbent, Preparation Method Therefor, and Cesium Removal Method Using Same

Номер: US20190210004A1
Автор: BAE Sang Eun, Cho Young Jin, Lim Sang Ho, PARK Jai Il, Park Tae Hong, YEON Jei Won, YOUN Young Sang
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present invention relates to a magnetic cesium adsorbent, a preparation method therefor, and a cesium removal method using the same, the preparation method comprising the steps of: (a) preparing a metal hexacyanoferrate; and (b) hydrothermally reacting the metal hexacyanoferrate so as to prepare a metal hexacyanoferrate having a rhombohedral crystal structure. 1. A method of preparing a magnetic cesium adsorbent , comprising:(a) preparing a metal hexacyanoferrate; and(b) preparing a metal hexacyanoferrate having a rhombohedral crystal structure through a hydrothermal reaction of the metal hexacyanoferrate.2. The method according to claim 1 , wherein claim 1 , in step (a) claim 1 , the metal hexacyanoferrate has a cubic crystal structure.3. The method according to claim 1 , wherein claim 1 , in the metal hexacyanoferrate in step (a) claim 1 , the carbon atoms of the cyano ligands form six coordinate bonds with the ferric ion claim 1 , and the nitrogen atoms of the cyano ligands form six coordinate bonds with a metal ion.4. The method according to claim 3 , wherein the metal ion is a nickel or manganese ion.5. The method according to claim 1 , wherein the hydrothermal reaction in step (b) is performed at 120 to 200° C. under a pressure of 2 to 15 bar for 20 minutes to 20 hours.6. The method according to claim 1 , further comprising:after the hydrothermal reaction in step (b), removing and drying water or an aqueous solution.7. A magnetic cesium adsorbent comprising a metal hexacyanoferrate having a rhombohedral crystal structure.8. The adsorbent according to claim 7 , wherein claim 7 , when the metal ion is a nickel ion claim 7 , the metal hexacyanoferrate having a rhombohedral crystal structure shows XRD peaks at 17 claim 7 , 24 claim 7 , 25 claim 7 , 35 claim 7 , 38.5 claim 7 , 39.8 claim 7 , 49.5 claim 7 , 51 claim 7 , 53.5 claim 7 , 56.2 and 57.4 2θ (±0.2°).9. The adsorbent according to claim 7 , wherein claim 7 , when the metal ion is a manganese ion claim 7 ...

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Номер записи: 86
02-08-2018 дата публикации

HYBRID SAFETY INJECTION TANK SYSTEM PRESSURIZED WITH SAFETY VALVE OF PRESSURIZER

Номер: US20180218796A1
Автор: Baek Won Pil, KIM Kihwan, Kwon Tae-Soon, Song Chul-Hwa, Yang Joon-Eon
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

A hybrid safety injection tank system. The system is pressurized with a safety valve of a pressurizer, which functions as a low pressure safety injection tank and as a high pressure core makeup tank of a nuclear reactor emergency core cooling system. The safety valve is configured to be automatically operated in response to a pressure difference and is installed on a pressure equalization pipe that can realize pressure equalization between the low pressure safety injection tank and the high pressure pressurizer in the event of the nuclear power plant station blackout and power outage. 1. A hybrid safety injection tank system pressurized with a safety valve of a pressurizer , comprising:an emergency core cooling water safety injection tank (SIT) charged both with cooling water and with nitrogen gas for cooling a nuclear reactor system;a pressurizer for supplying high pressure steam to pressurize the safety injection tank;a pressure equalization pipe connecting the safety injection tank to the pressurizer so as to realize pressure equalization between the safety injection tank and the pressurizer;a pressure equalization pipe isolation valve installed on the pressure equalization pipe so as to isolate the safety injection tank from the pressurizer;a pressure equalization pipe check valve installed on the pressure equalization pipe in series with the pressure equalization pipe isolation valve so as to prevent a backflow from the safety injection tank to the pressurizer; anda safety valve installed on the pressure equalization pipe in parallel both with the pressure equalization pipe isolation valve and with the pressure equalization pipe check valve so as to isolate the safety injection tank from the pressurizer.2. The hybrid safety injection tank system pressurized with the safety valve of the pressurizer as set forth in claim 1 , further comprising:an emergency core cooling water injection pipe connecting the safety injection tank to the nuclear reactor system;a ...

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Номер записи: 87
03-08-2017 дата публикации

SYSTEM AND METHOD FOR PREVENTING AND MONITORING LEAKAGE OF WATER FROM TANK LINER

Номер: US20170221592A1
Автор: JUNG Un-Soo, KWAK Byung Ho, LEE Jong Min, RYU Jeong-Soo
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Disclosed are a system and method for preventing and monitoring a leakage of water from a tank liner at a storage tank having: a concrete reservoir; the tank liner made up of a wall liner that is formed by coupling a plurality of first panels and is attached to an inner wall of the concrete reservoir, and a floor liner that is formed by coupling a plurality of second panels, is attached to a floor of the concrete reservoir, and is coupled to the wall liner by welding; a leaking water collecting plate formed by welding a plurality of third panels and inserted between the floor liner and the floor of the concrete reservoir; and an edge leaking water collecting channel buried in an edge of the storage tank and configured to collect leaking water discharged between the floor liner and the leaking water collecting plate. 1. A system for preventing and monitoring a leakage of water from a tank liner at a storage tank , the system comprising:a concrete reservoir;the tank liner made up of a wall liner that is formed by coupling a plurality of first panels and is attached to an inner wall of the concrete reservoir, and a floor liner that is formed by coupling a plurality of second panels, is attached to a floor of the concrete reservoir, and is coupled to the wall liner by welding;a leaking water collecting plate formed by welding a plurality of third panels and inserted between the floor liner and the floor of the concrete reservoir; andan edge leaking water collecting channel buried in an edge of the storage tank and configured to collect leaking water discharged between the floor liner and the leaking water collecting plate.2. The system according to claim 1 , further comprising a wall leaking water collecting channel that is buried in a wall of the concrete reservoir on an outer surface of the wall liner claim 1 , is formed along a weld zone between the first panels at a long length claim 1 , and is coupled to the edge leaking water collecting channel at a lower portion ...

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Номер записи: 88
23-10-2014 дата публикации

EPOXY RESIN COMPOSITION FOR NEUTRON SHIELDING, AND METHOD FOR PREPARING THE SAME

Номер: US20140312536A1
Автор: Bae Yeon-Joo, Jun Ji-Heon, KIM Jae-woo
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A method of manufacturing an epoxy resin composition for neutron shielding , comprising:obtaining a mixture of a curing agent and a powder by mixing an amine-based curing agent with either a boron compound powder for neutron absorption or a powder selectively containing a gamma ray attenuation, high density metal powder and a flame retardant powder or with a mixture thereof;performing an ultrasonic wave treatment by applying ultrasonic waves to the mixture to coat the powder surface with the amine-based curing agent, simultaneously with allowing powder particles to be dispersed in the curing agent; andmixing the amine-based curing agent including the ultrasonic wave-treated and dispersed powder particles with an epoxy resin to then be dispersed.2. The method of claim 1 , wherein the boron compound is at least one selected from a group consisting of BC claim 1 , BN claim 1 , BOand B(OH) claim 1 , the high density metal powder is at least one selected from a group consisting of Fe claim 1 , Ni claim 1 , Cu ...

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Номер записи: 89
23-10-2014 дата публикации

TECHNETIUM-99M LABELED COMPLEX OF GOLD NANOPARTICLE-GOLD BINDING PEPTIDES, AND METHOD OF MAKING AND USING THE SAME

Номер: US20140314668A1
Автор: Jang Beom Su, Lee Joo-Sang, PARK Sang Hyun, Rho Jong-Kook
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

There is provided a method for preparing a Tc labeled gold nanoparticles-gold binding peptide, including: (a) coating gold nanoparticles with a gold binding peptide; and (b) labeling a composed Tc tricarbonyl precursor on the gold binding peptide coated on the gold nanoparticles. The Tc labeled gold nanoparticles-gold binding peptide prepared by the method according to the present invention is expected to be usefully employed for manufacturing a molecular contrast agent (imaging agent) which is traceable in organisms using imaging apparatuses such as gamma imaging and single photon emission computed tomography due to high labeling yield and good in-vivo stability. 1. A method of preparing a technetium-99m labeled complex of gold nanoparticle-gold binding peptides , the method comprising:mixing gold nanoparticles with gold binding peptides to attach gold binding peptides to a surface of a gold nanoparticle; andlabeling with a technetium-99m tricarbonyl precursor at least part of the gold binding peptides attached to the gold nanoparticle.2. The method of claim 1 , wherein the gold binding peptides comprise an amino acid sequence of SEQ ID No. 1.3. A technetium-99m labeled complex of gold nanoparticle-gold binding peptides claim 1 , the complex comprising:a gold nanoparticle;gold binding peptides attached onto a surface of the gold nanoparticle; anda technetium-99m labeling connected to at least part of the gold binding peptides.4. A molecular imaging agent comprising the technetium-99m labeled complex of gold nanoparticle-gold binding peptides of .5. A nuclear medicine imaging contrast agent comprising the technetium-99m labeled complex of gold nanoparticle-gold binding peptides of .6. A method of molecular imaging claim 3 , the method comprising:{'claim-ref': {'@idref': 'CLM-00004', 'claim 4'}, 'administering the molecular imaging agent of to a subject in need of such imaging; and'}monitoring behavior of the agent in the subject using an imaging system. This ...

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Номер записи: 90
11-08-2016 дата публикации

MEASURING DEVICE FOR MICRO FLOW RATE AND NUCLEAR POWER PLANT HAVING THE SAME

Номер: US20160232997A1
Автор: KIM Keungkoo, KIM Myungjun, KIM Youngin, LEE Heejoon, MOON Joohyung
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Provided is a device for measuring a micro flow rate. The device includes a container having an internal space for containing a fluid flowing therein and an inflow line and an outflow line formed in communication with the internal space, a fluid level gauge configured to sense whether a level of a fluid collected in the container rises to a predetermined height to conduct or block flow of an electric current, a control valve disposed in the outflow line and configured to open or close the outflow line according to a state in which the control valve is electrically connected to or disconnected from the fluid level gauge such that the outflow line is opened or closed according to a change in the fluid level; and a control unit configured to calculate a micro flow rate of the fluid collected in the container using information acquired from at least one of the fluid level gauge and the control valve. 1. A device for measuring a micro flow rate , the device comprising:a container having an internal space for containing a fluid flowing therein and an inflow line and an outflow line formed in communication with the internal space;a fluid level gauge configured to sense whether a level of a fluid collected in the container rises to a predetermined height to conduct or block flow of an electric current;a control valve disposed in the outflow line and configured to open or close the outflow line according to a state in which the control valve is electrically connected to or disconnected from the fluid level gauge such that the outflow line is opened or closed according to a change in the fluid level; anda control unit configured to calculate a micro flow rate of the fluid collected in the container using information acquired from at least one of the fluid level gauge and the control valve.2. The device of claim 1 , wherein the control unit is configured to measure a volume of fluid discharged when the control valve is opened and a time interval between opening or closing ...

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Номер записи: 91
27-08-2015 дата публикации

PASSIVE CONTAINMENT AIR COOLING DEVICE AND SYSTEM WITH ISOLATED PRESSURE BOUNDARY

Номер: US20150243382A1
Автор: BAE Sung Won, KIM Kihwan, Kwon Tae-Soon, Park Hyun Sik, Park Yusun
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A passive containment air cooling device with an isolated pressure boundary , comprising: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; anda cooled air exhaust unit formed in the air induction duct to increase cooling efficiency of the heat exchanger.2. The device as set forth in claim 1 , wherein the heat exchanger comprises:a containment internal heat exchanger exposed to an inside of the containment;a containment external heat exchanger exposed to an outside of the containment;a gas phase connection pipe penetrating through the outer wall of the containment and connecting a side of an upper part of the containment internal heat exchanger and a side of an upper part of the containment external heat exchanger; anda liquid phase connection pipe penetrating through the outer wall of the containment and connecting a side of a lower part of the containment internal heat exchanger and a side of a lower part of the containment external heat exchanger.3. The device as set forth in claim 2 , wherein the containment internal heat exchanger claim 2 , the containment external heat exchanger claim 2 , the gas phase connection pipe claim 2 , and the liquid phase connection pipe constitute a closed loop.4. The device as set forth in claim 2 , wherein ...

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Номер записи: 92
27-08-2015 дата публикации

WATER-AIR COMBINED PASSIVE FEED WATER COOLING APPARATUS AND SYSTEM

Номер: US20150243383A1
Автор: BAE Sung Won, KIM Kihwan, Kwon Tae-Soon, Park Hyun Sik, Park Yusun
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A water-air combined passive feed water cooling apparatus comprising: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 comprising 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; anda condensed water collecting pipe for refilling the cooling tank with the steam liquefied by the air cooling heat exchanger.2. The apparatus of claim 1 , wherein the cooling tank is formed of a pressure vessel.3. The apparatus of claim 1 , wherein the air cooling heat exchanger comprises a radiator receiving steam of cooling water generated in the cooling tank through the evaporative steam pipe and emitting heat ...

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Номер записи: 93
27-08-2015 дата публикации

COOLING WATER SUPPLY TANK HAVING HEAT MIXING PREVENTION FUNCTION AND PASSIVE HIGH-PRESSURE SAFETY INJECTION SYSTEM AND METHOD USING THE SAME

Номер: US20150243384A1
Автор: KIM Kihwan, Kwon Tae-Soon
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A cooling water supply tank having a heat mixing prevention function , the cooling water supply tank supplying cooling water using steam compressed by a compressor , and comprisingan internal circulation prevention structure for preventing the cooling water from circulating in the cooling water supply tank.2. The cooling water supply tank as set forth in claim 1 , wherein the internal circulation prevention structure comprisesat least one cooling water guide preventing the cooling water from moving in the cooling water supply tank, the cooling water guide partitioning at least a portion of an internal space of the cooling water supply tank into a plurality of areas.3. The cooling water supply tank as set forth in claim 2 , wherein the cooling water guide comprises at least one vertical partition.4. The cooling water supply tank as set forth in claim 2 , wherein a height of the cooling water guide is greater than a level of cooling water in the cooling water supply tank when the cooling water supply tank is in a standby state before being operated.5. The cooling water supply tank as set forth in claim 2 , wherein the cooling water guide contains non-corrosive metal.6. The cooling water supply tank as set forth in claim 1 , wherein a cross-section of the internal circulation prevention structure has a shape selected from among a shape having a plurality of polygons claim 1 , a circular shape and a spiral shape.7. A passive high-pressure safety injection system having ...

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Номер записи: 94
25-07-2019 дата публикации

Curcumin Derivative, Method for Producing Same, and Photo-Acoustic Imaging Agent Comprising Same for Detecting Beta-Amyloid Plaque

Номер: US20190224344A1
Автор: Jung-Joon Min, Min-Goo Hur, Seung-dae Yang, Seung-Hwan Park, Seung-Jin JUNG, Yeong-Jin Hong, Yong-Dae Park
Принадлежит: Korea Atomic Energy Research Institute KAERI

The present invention relates to a curcumin derivative, a method for producing same, and a photo-acoustic imaging agent comprising the curcumin derivative for detecting beta-amyloid plaque. The curcumin derivative, expressed by chemical formula 1, according to the present invention exhibits superb selective bonding with beta-amyloid, thereby allowing beta-amyloid to be detected by means of an optical or photo-acoustic imaging methods, and, particularly, the curcumin derivative can highly effectively detect photo-acoustic signals with almost no noise by reacting to irradiation of light having a particular wavelength range, and thus can be useful as a composition for detecting beta-amyloid and for diagnosing diseases caused by excessive production of beta-amyloid.

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Номер записи: 95
16-08-2018 дата публикации

NUCLEAR POWER PLANT

Номер: US20180233240A1
Автор: BAE Young Min, CHOI Suhn, Han Hun Sik, Kim Keung Koo, Kim Young In
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Disclosed is a nuclear power plant which drives a Stirling engine by means of heat generated in nuclear power plant safety systems during an accident, uses the resulting power directly or generates electric power so as to supply the power to the safety systems, and thus can improve economic efficiency as well as the reliability of safety systems, such as a passive safety system, by operating the safety systems without an emergency diesel generator or external electric power. 1. A nuclear power plant , comprising:a nuclear safety system configured to remove at least one of heat in a reactor coolant system and heat transferred from the reactor coolant system to a containment to an outside of the containment when an accident occurs in the nuclear power plant;a power generator provided with a heat exchange unit to receive heat removed to an outside of the containment, and provided with a cylinder to generate power by heat received through the heat exchange unit; anda heat transfer portion configured to provide a flow path of heat transfer fluid between the reactor coolant system and the power generator or between the containment and the power generator to transfer the heat removed to an outside of the containment to the power generator.2. The nuclear power plant of claim 1 , wherein the nuclear safety system comprises a passive safety system configured to remove heat in the reactor coolant system or heat transferred from the reactor coolant system to the containment by fluid circulation claim 1 , and the passive safety system comprises at least one of an air-cooling and a water-cooling heat exchanger.3. The nuclear power plant of claim 2 , wherein the heat exchanger is a plate type or shell-and-tube type heat exchanger.4. The nuclear power plant of claim 2 , wherein the fluid is at least one of air claim 2 , cooling water claim 2 , steam claim 2 , and a mixed fluid obtained by mixing air with steam or steam with cooling water.5. The nuclear power plant of claim 1 , ...

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Номер записи: 96
25-08-2016 дата публикации

PASSIVE SAFETY EQUIPMENT AND NUCLEAR POWER PLANT INCLUDING SAME

Номер: US20160247585A1
Автор: CHOI Suhn, HA Jae Joo, Han Hun Sik, KANG Kyung Jun, Kim Keung Koo, Kim Young In, MOON Joo Hyung, Park Cheon Tae, RYU Seung Yeob, YI Sung Jae, YUN Ju Hyeon
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

The present invention provides passive safety equipment, comprising: a cooling part formed to cool a first fluid, which is emitted from a reactor coolant system or a steam generator, and a second fluid in a housing; and a circulation induction sprayer which is formed to spray the first fluid emitted from the reactor coolant system or the steam generator into the cooling part, has at least part thereof open to the inside of the housing such that the second fluid flows thereinto according to a drop in pressure caused by the spraying of the first fluid, and sprays the second fluid with the inflown first fluid. 1. A passive safety facility , comprising:a cooling section formed to cool a first fluid discharged from a reactor coolant system or steam generator along with a second fluid within a containment; anda circulation inducing jet device formed to jet the first fluid discharged from the reactor coolant system or the steam generator to the cooling section, at least part of which is open toward an inside of the containment to entrain the second fluid by a pressure drop caused while jetting the first fluid so as to jet the entrained second fluid along with the first fluid.2. The passive safety facility of claim 1 , wherein the circulation inducing jet device comprises:a first fluid jetting section connected to the reactor coolant system or the steam generator to receive the first fluid, and formed to jet the received first fluid;a second fluid entraining section formed in an annular shape around the first fluid jetting section to entrain the second fluid within the containment; anda circulating fluid jetting section configured to surround the first fluid jetting section with a portion having an inner diameter larger than that of the first fluid jetting section to form the second fluid entraining section, and supply the first fluid and the second fluid to the cooling section.3. The passive safety facility of claim 2 , wherein the first fluid jetting section comprises a ...

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Номер записи: 97
13-11-2014 дата публикации

COOLING SYSTEM OF EMERGENCY COOLING TANK AND NUCLEAR POWER PLANT HAVING THE SAME

Номер: US20140334590A1
Автор: BAE Young Min, HA Jae Joo, Kim Keung Koo, KIM Tae Wan, Kim Young In, Lee Won Jae, YOON Ju Hyeon
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A cooling system of an emergency cooling tank , comprising: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 a fluid within the emergency cooling tank and the air such that the operation of the ...

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Номер записи: 98
13-11-2014 дата публикации

PASSIVE CONTAINMENT SPRAY SYSTEM

Номер: US20140334591A1
Автор: HA Jae Joo, KANG Han Ok, Kim Keung Koo, KIM Tae Wan, Kim Young In, SHIN Soo Jai, YOON Ju Hyeon
Принадлежит: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

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. 1. A passive containment spray system comprising:a spray coolant storage unit that communicates with a containment accommodating a reactor vessel and maintains equilibrium of pressure with 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; anda connection pipe having one end inserted into the spray coolant storage unit to provide a flow path along which the coolant flows, and the other end connected to the spray pipe to supply the coolant passively to the spray pipe when the pressure within the containment increases due to an occurrence of an accident and a flow of the coolant occurs therein.2. The passive containment spray system of claim 1 , wherein the connection pipe includes:an upward flow path portion inserted into the spray coolant storage unit, and providing a flow path along which the coolant flows when the pressure within the containment increases, the upward flow path extending up to a ...

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Номер записи: 99
01-08-2019 дата публикации

Nondestructive inspection system

Номер: US20190235124A1
Автор: Byeongno LEE, Changgoo KANG, Hansoo Kim, Jungho MUN, Kyungmin OH, Moonsik CHAE, Namho LEE, Soomin Lee
Принадлежит: Korea Atomic Energy Research Institute KAERI

Disclosed is a nondestructive inspection system includes: a radiation source system generating different types of radiations and irradiating the generated different types of radiations toward an inspection object; a detector system detecting each of the radiations transmitted through the inspection object; a transfer system varying a position of the inspection object such that the radiations generated by the radiation source system are irradiated to the inspection object; and an image system generating an image regarding the inspection object on the basis of a detection result from the detector system, wherein the radiation source system comprises: an electron gun generating an electron beam; an electron accelerator accelerating the electron beam generated by the electron gun; and a target system selectively generating at least one of various types of radiations according to variables when the electron beam accelerated by the electron accelerator is irradiated thereto.

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Номер записи: 100