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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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Применить Всего найдено 73. Отображено 73.
14-06-2016 дата публикации

METHOD TO MANUFACTURE ZIRCONIUM COMPONENT FOR NUCLEAR FUEL BY APPLYING MUTI-STAGE HOT ROLLING PROCESS

Номер: KR101630403B1
Автор: MOK, YONG KYOON, KIM, YOON HO, JUNG, TAE SIK, LEE, SUNG YONG, JANG, HUN, LEE, CHUNG YONG, NA, YEON SOO, CHOI, MIN YOUNG, KO, DAE GYUN, LEE, SEUNG JAE, KIM, JAE IK
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention provides a manufacturing method of a zirconium alloy component which evenly distributes a precipitate of an average size equal to or less than 35 nm to an inside of a base through a multi-stage hot rolling process. The manufacturing method of the zirconium alloy component comprises: (step 1) a step of making an ingot of a zirconium alloy containing niobium; (step 2) a step of rapidly cooling the ingot manufactured in step 1 after thermally processing the ingot at a beta-zirconium phase temperature; (step 3) a step of preheating the ingot rapidly cooled in step 2 before a hot rolling process; (step 4) a multi-stage hot rolling step of performing a secondary hot rolling process which follows a primary hot rolling process and an air cooling process right after the preheating of step 3; (step 5) a step of performing a primary cold rolling process after primarily performing a primary middle thermal process on a multi-stage hot rolled material produced in step 4; (step 6 ...

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Номер записи: 1
13-05-2016 дата публикации

Pressureless sintered silicon carbide ceramics with high fracture toughness and high hardness, compositions thereof and Process for producing the Same

Номер: KR0101620510B1
Автор: 김영욱, 엄정혜, 서유광, 이승재
Принадлежит: 서울시립대학교 산학협력단, 한전원자력연료 주식회사

... 본 발명은 고인성과 고경도를 갖는 상압소결 탄화규소 소재 제조용 조성물, 탄화규소 소재 및 소재의 제조방법에 관한 것으로서, 보다 상세하게는 탄화규소 분말과 소결첨가제로서 Al2O3, AlN, Y2O3를 포함하는 구성을 특징으로 하는 탄화규소 소재 제조용 조성물과, 이를 이용하여 제조되어 소결 밀도가 3.10 ~ 3.40 g/cm3 범위이고, 파괴인성이 6.2 ~ 8.5 MPa?m1/2이며, 경도가 26 ~ 30 GPa 범위로 매우 우수한 상압소결법을 사용하여 공정이 간단한 탄화규소 소재의 제조방법을 제공한다. 이상과 같은 본 발명에 따르면, 본 발명은 소결첨가제로서 Al2O3, AlN, Y2O3을 포함하는 소결첨가제를 사용함으로써, 고가의 나노 크기 탄화규소 입자 대신 서브마이크론(submicron) 크기의 베타상 탄화규소와 알파상 탄화규소 분말을 사용함에도 불구하고, 소결첨가제가 탄화규소 표면의 SiO2와 반응하여 사성분계 액상이 서로 상승작용을 일으키고, 입자 성장을 가속화하기 위한 종자 입자로 첨가된 알파상 탄화규소가 상기 사성분계 액상에서 β-SiC→α-SiC 상변태를 촉진함으로써 탄화규소의 치밀화와 입자성장을 촉진시키므로, 1900℃ 이하의 낮은 온도에서 상압소결 공정만으로 탄화규소의 치밀화가 가능한 작용효과가 기대된다.

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Номер записи: 2
11-03-2016 дата публикации

NUCLEAR FUEL ASSEMBLY HAVING FUNCTIONS TO PREVENT FLOW-INDUCED VIBRATION AND INFLOW OF DEBRIS IN ICI TUBE

Номер: KR101602169B1
Автор: LEE, HAK IN, KIM, JAE IK, JEON, SANG YOUN, EOM, KYONG BO, HA, DONG GEUN, KIM, SEONG SOO, RYU, JOO YOUNG, KWON, O CHEOL, RYU, SU PIL, KIM, JIN SUN, CHUN, JOO HONG, KIM, BA LEUM
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a nuclear fuel assembly having functions to prevent flow-induced vibration and an inflow of debris in ICI tube. The nuclear fuel assembly comprises: a number of fuel rods (110) arranged in an axial direction; a number of supporting grids (120) prepared to support the fuel rods (110); a number of guide tubes (130) fixed with the supporting grid (120) and comprising an assembly frame; a measurement tube (160) which is supported by the support grid (120) and into which an in-core instrument (170) is inserted through the upper part; an upper part fixing body (140) supporting the upper part of the guide tube (130); a lower part fixing body (150) which supports the lower part of the guide tube (130) and has many air passage holes formed thereon. The lower end part of the measurement tube (160) includes a stopper (161) assembled by penetrating through the lower part fixing body (150) and supporting the front end of the in-core instrument (170) in the inside of ...

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Номер записи: 3
09-11-2016 дата публикации

핵연료집합체용 지지격자의 레이저 용접방법

Номер: KR0101673881B1
Автор: 오병은, 윤광호, 신동광, 한상재, 홍종승, 홍운수
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 핵연료집합체용 지지격자의 레이저 용접방법에 관한 것으로, 복수의 기준마커가 마련된 용접치구에 의해 가조립되어 레이저 용접이 이루어지는 핵연료집합체용 지지격자의 레이저 용접방법으로서, 상기 기준마커의 위치 좌표를 기준으로 영상정보를 추출하는 제1단계(S10)와; 제1단계(S10)에서 추출된 영상정보에서 기준마커에 대한 위치좌표를 보정하는 제2단계(S20)와; 보정된 기준마커의 위치좌표를 기준으로 용접점에 대한 레이저 용접을 실시하는 제3단계(S30);를 포함한다.

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Номер записи: 4
07-11-2017 дата публикации

AMMONIUM URANATE HYDRATE (AUH) CRYSTAL WITH LARGE PARTICLE SIZE, AND METHOD AND APPARATUS FOR PREPARING SAME

Номер: KR101793193B1
Автор: BAE, YOUNG MOON, YANG, SEUNG CHUL, LEE, BYUNG KUK, KWAK, DONG YONG, CHO, HYUN KWANG, GU, SUNG HOI, HWANG, EUI JUN
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to an ammonium uranate hydrate crystal with a large particle size, and a method for preparing the ammonium uranate hydrate crystal with the large particle size. The method of the present invention comprises injecting gas ammonia into an aqueous uranyl nitrate solution to control the reaction rate instead of a conventional method comprising making the aqueous uranyl nitrate solution react with ammonia water in an ammonium diuranate (ADU) process. Therefore, the method according to the present invention can increase a particle diameter of the ammonium uranate hydrate crystal that is formed. The ammonium uranate hydrate crystal finally prepared by the method had an average particle size of 9.32 to 14.68 μm as a test result and the average particle size was 100 times or larger than that of the crystal prepared by the conventional method using the ADU process. Further, as an analysis result of a filtrate, the ammonium uranate hydrate crystal had less than 1 ppm ...

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Номер записи: 5
16-09-2015 дата публикации

FUEL ROD AUTO-LOADING APPARATUS FOR NUCLEAR FUEL ASSEMBLY

Номер: KR101553260B1
Автор: NA, TAE HYUNG, HAN, SANG JAE, HONG, JONG SUNG, YANG, KYUNG HWAN
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a fuel rod auto-loading apparatus classifying and loading fuel rods completely assembled into unit components. The fuel rod auto-loading apparatus comprises: a loading unit (100) having a plurality of loading parts (110) stacked to allow a plurality of fuel rods to be horizontally stored; a loading unit (200) elevating the fuel rods completely assembled into the unit components to the loading part (110) in accordance with a bar code marked on each fuel rod to be carried; an unloading unit (300) selectively unloading a specific fuel rod of the fuel rods stored in the loading part (110); a bar code reader (400) decoding the bar code marked on the surface of a fuel rod entering the loading unit (200) along a transferring line; a rotation operational part (500) driving the fuel rod entering the loading unit (200) to be rotated at a predetermined angle; and a control unit (600) driving the loading unit (200) in accordance with history information of the fuel ...

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Номер записи: 6
03-03-2017 дата публикации

SPACER GRID FOR NUCLEAR FUEL ASSEMBLY HAVING IMPROVED ISOTROPIC SUPPORT STRUCTURE

Номер: KR101711546B1
Автор: RYU, JOO YOUNG, JEON, SANG YOUN, EOM, KYONG BO, HA, DONG GEUN, KIM, JIN SUN, KIM, SEONG SOO, KWON, O CHEOL, RYU, SU PIL, CHUN, JOO HONG, KIM, BA LEUM, NAM, CHAE YOUNG
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

Disclosed is a support grid for a nuclear fuel assembly having an improved isotropic support structure, which is capable of stably supporting a fuel rod. According to the present invention, provided is the support grid comprising: a plurality of grid plates (100) each having a grid spring, which are intersected in a grid form to support a fuel rod disposed in a partitioned cell. The grid spring (110) is formed to intersect with the top and bottom of a through hole (101) formed to penetrate the grid plate (100) in a longitudinal direction. A first fuel rod contract unit (111) protrudes from one side with respect to a grid surface and a second fuel rod contract unit (112) extends downward from the first fuel rod contract unit (111) and protrudes from the other side with respect to the grid surface. COPYRIGHT KIPO 2017 ...

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Номер записи: 7
05-02-2016 дата публикации

Scrap metal sorting device

Номер: KR0101591914B1
Автор: 신중철, 김인규, 문종한, 윤주필, 한상진, 김동휘, 이지은
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 금속스크랩이 레이저 분광분석에 의하여 성분에 따라 분류될 수 있는 금속스크랩 분류장치에 관한 것으로, 금속스크랩 투입부(10)와, 금속스크랩 투입부(10)에 의하여 투입된 금속스크랩을 이송라인을 따라서 이송하되, 레이저 조사를 위한 관통영역(T)이 구비된 이송부(20)와, 이송부(20) 하부에 배치되어 관통영역(T)을 통해 금속스크랩에 레이저를 조사하게 되는 레이저 헤드(42)가 마련되어 방출된 플라즈마를 여기원으로 하여 시료의 성분에 대한 분석이 이루어지는 레이저 분석부(40)와, 레이저 헤드(40)와 대향하여 이송부(20)의 상부에 마련되어 수평이송이 이루어지는 금속스크랩을 가압하여 이송방향으로 안내하게 되는 가압부(30)와, 이송라인을 따라 이송되는 금속스크랩의 분류가 이루어지는 분류부(50)와, 분석부(40)에서 검출된 금속스크랩의 성분에 따라서 상기 분류부(50)를 제어하여 금속스크랩을 분류하게 되는 제어부를 포함하여, 이송중인 여러 가지 형상의 금속스크랩에 조사되는 레이저 빔의 초점이 금속스크랩의 표면에 진동없이 정확하게 맺힐 수 있게 되는 금속스크랩 분류장치를 제공하고자 한다.

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Номер записи: 8
06-12-2018 дата публикации

APPARATUS FOR TESTING OXIDATION PERFORMANCE IN HIGH-TEMPERATURE WATER VAPOR

Номер: KR101907428B1
Автор: LIM, KWANG YOUNG, NA, YEON SOO, LEE, SEUNG JAE, KIM, YOON HO, JANG, HUN, YOO, JONG SUNG
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to an apparatus for testing oxidation performance in high-temperature water vapor, capable of evaluating oxidation resistance performance and thermal shock resistance of the high-temperature water vapor in a specimen under a condition in which the water vapor rapidly flows at a high temperature in order to simulate a serious accident of a nuclear reactor. The apparatus includes: a water tank for storing water; a water vapor generation unit for receiving the water from the water tank to generate water vapor; a first conduit for connecting the water tank to the water vapor generation unit; a second conduit in which the water vapor generated from the water vapor generation unit flows, and a band heater is installed on an outer peripheral surface of the second conduit; an inert gas introduction pipe formed in the first conduit and the second conduit; a ceramic tube connected to the second conduit to allow the water vapor to flow therein, and having a plurality ...

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Номер записи: 9
16-12-2016 дата публикации

SYSTEM TO SET TOLERANCE OF CORRELATION BY USING REPETITIVE CROSS-VALIDATION AND METHOD THEREOF

Номер: KR101687169B1
Автор: KIM, KANG HOON, KIM, BYEUNG SEOK, NAHM, KEE YIL
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a system to set tolerance of a correlation by using repetitive cross-validation and a method thereof, to prevent distortion of data characteristics due to accidental or human interference in correlation optimization and tolerance setting, and risk thereby, or quantize effect thereof. According to the present invention, the system comprises: a variable extraction unit classifying training sets and validation sets, and optimizing a correlation coefficient to extract variables; a normality verification unit to verify normality according to a variable extraction result; and a departure from nucleate boiling ratio (DNBR) limit unit and a control unit to verify whether an identical mother group is present depending on the normality and to determine tolerance of a DNBR from a tolerance distribution. COPYRIGHT KIPO 2016 (100) Variable extraction unit (110) Initialization module (120) Correlation coefficient optimization module (130) Extraction module (140) Location ...

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Номер записи: 10
24-04-2017 дата публикации

SUPPORT GRID OF NUCLEAR FUEL ASSEMBLY

Номер: KR101729155B1
Автор: CHUN, JOO HONG, JEON, SANG YOUN, EOM, KYONG BO, HA, DONG GEUN, KIM, JIN SUN, KIM, SEONG SOO, RYU, JOO YOUNG, KWON, O CHEOL, RYU, SU PIL, KIM, BA LEUM, NAM, CHAE YOUNG
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a support grid of a nuclear fuel assembly, having a grid spring structure implementing low rigidity of a spring to allow easy insertion of a fuel rod while having proper reaction to secure soundness in supporting the fuel rod. In the support grid of a nuclear fuel assembly including a plurality of grid plates (100) having each grid spring (110) to support fuel rods arranged inside cells formed by division through grid-shaped crossing, the grid spring (110) comprises: a fuel rod contact part (111) supporting a fuel rod in a vertical direction; a pair of upper legs (112) extending upward from the grid plate (100) to be aligned to both side parts of the fuel rod contact part (111) and connected with both side ends of the fuel rod contact part (111), respectively; and a pair of lower legs (113) extending downward from the grid plate (100) to be aligned to the both side parts of the fuel rod contact part (111) and connected with the both side ends of the fuel ...

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Номер записи: 11
03-03-2017 дата публикации

APPARATUS FOR CONTROLLING INTERFACE IN LIQUID-LIQUID EXTRACTION COLUMN BY USING PRESSURE EQUILIBRIUM

Номер: KR101710906B1
Автор: BAE, YOUNG MOON, YANG, SEUNG CHUL, LEE, BYUNG KUK, KWAK, DONG YONG, CHO, HYUN KWANG
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to an apparatus for controlling an interface in a liquid-liquid extraction column by using pressure equilibrium, and more particularly to an apparatus for controlling an interface in a liquid-liquid extraction column by using pressure equilibrium, in which a vertical pipe is installed on one side of an extraction column so as to be parallel to the extraction column and which enables pressure applied to an inside of the extraction column and pressure applied to an inside of the vertical pipe to be artificially in equilibrium through movement of a liquid from the extraction column to the vertical pipe, thereby enabling an interface between two liquids, having been introduced into a top head of the extraction column and having different specific gravities, to be constantly maintained by using simple control system configurations. For this purpose, provided is apparatus for controlling an interface in a liquid-liquid extraction column, the apparatus comprising: ...

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Номер записи: 12
15-09-2015 дата публикации

JIG TO MANUFACTURE PILGER DIE

Номер: KR101552512B1
Автор: SHIN, JUNG CHEOL, KIM, IN KYU, PARK, KI BUM, PARK, MIN YOUNG, BAE, DONG JIN
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a jig to manufacture a pilger die to process a groove of a pilger die. A jig to process a groove on an edge surface of a pilger die comprises: a fixed bracket (110) wherein an axial hole of a pilger die material is placed in a horizontal direction, and a centering fixing unit (111) rotationally inserted is provided; a fixed plate (120) which is circular disk fixated by a coupling member by being in contact with one side surface while having a same axis as the axial hole of the pilger die material inserted into the centering fixing unit, and having an indexing unit (121) to determine at least two angles which are arranged to rotationally be symmetrical; and a fixing unit (130) fixedly supporting the fixed plate (120) on the fixed bracket (110). COPYRIGHT KIPO 2015 ...

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Номер записи: 13
10-10-2016 дата публикации

HOLD-DOWN SPRING UNIT FOR TOP FIXTURE HAVING IMPROVED ON-OFF CHARACTERISTICS, AND TOP FIXTURE FOR NUCLEAR FUEL ASSEMBLY HAVING SAME

Номер: KR101663125B1
Автор: KIM, SEONG SOO, KIM, JAE IK, JEON, SANG YOUN, EOM, KYONG BO, HA, DONG GEUN, KIM, JIN SUN, RYU, JOO YOUNG, KWON, O CHEOL, RYU, SU PIL, LEE, HAK IN, CHUN, JOO HONG, KIM, BA LEUM, NAM, CHAE YOUNG
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a hold-down spring unit for a top fixture having improved on-off characteristics, which generates hold-down force required at accurate on-off points, and a top fixture for a nuclear fuel assembly having the same. The hold-down spring unit according to an embodiment of the present invention comprises: a first leaf spring (110) having one end fixed to a spring clamp (21) and the other end provided with a first rod portion (111) downwardly bent; at least one second leaf spring (120) having one end overlapping the first leaf spring (110) to be fixed to the spring clamp (21), and the other end provided with a rod insertion hole (121) into which the first rod portion (111) is inserted; and a third leaf spring (130) having one end overlapping the second leaf spring (120) to be fixed to the spring clamp (21), the other end provided with a second rod portion insertion hole (131) into which the first rod portion (111) is inserted, and with a second rod portion (132 ...

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Номер записи: 14
23-05-2018 дата публикации

UPPER END FIXATION BODY HAVING FLOW CHANNEL PLATE IN SHAPE OF WAVE FOR NUCLEAR FUEL ASSEMBLY

Номер: KR0101859524B1
Автор: KIM, BA LEUM, KIM, SEONG SOO, CHUN, JOO HONG, PARK, NAM GYU, YOO, JONG SUNG
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to an upper end fixation body for a nuclear fuel assembly and, more specifically, to an upper end fixation body having a flow channel plate in the shape of wave for a nuclear fuel assembly to enable an upper end fixation body of the nuclear fuel assembly and a fuel rod to maintain a certain distance from each other. According to the present invention, the upper end fixation body (100) having a flow channel plate in the shape of wave for a nuclear fuel assembly, as an upper end fixation body for a nuclear fuel assembly, comprises: a guide pipe joining unit (104) which is formed on a lower portion to connect a guide pipe; a measurement pipe joining unit (106) which connects a measurement pipe; and the flow channel plate (102) having many flow channel holes (108) to allow cooling water to flow. On a lower side of the flow channel plate (102), cut-out units (110) in the shape of a hemisphere are formed in a first direction of the flow channel plate (102) to maintain ...

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Номер записи: 15
20-11-2015 дата публикации

AUTOMATIC SYSTEM FOR LBLOCA ANALYSIS

Номер: KR0101570048B1
Автор: 이재일, 이강문, 박주현, 김원호, 김인훈
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 냉각재상실사고 분석 시스템에 관한 것으로서, 대형 냉각재상실사고 분석 시 인적오류를 최소화하고, 시간 손실을 줄일 수 있으며, 품질관리의 효율성을 높일 수 있는 냉각재상실사고 분석 시스템 및 그 방법을 제공함에 그 목적이 있다. 이러한 목적을 달성하기 위한 본 발명은, 불확실도 변수들의 변위를 고려하여, 각 변수들에 임의의 값을 할당하여 다수개의 세트 조합을 생성하는 샘플링부; 상기 샘플링부를 통해 생성된 각 불확실도 변수들의 값을 발전소를 모사하는 코드입력에 반영하는 입력 생성부; 상기 입력 생성부를 통해 생성된 입력을 이용하여 실제 계산을 수행하는 계산부; 상기 계산부를 통해 계산된 결과 파일들에서 필요한 데이터들을 추출하는 데이터 추출부; 및 상기 데이터 추출부를 통해 추출된 데이터들을 바탕으로 최종 평가 결과를 도출하는 평가 결과 도출부; 를 포함한다.

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Номер записи: 16
28-08-2015 дата публикации

METHOD FOR RECOVERING URANIUM AND MANUFACTURING NUCLEAR FUEL PELLET BY POLYVINYL PYRROLIDONE-URANIUM COMPLEX

Номер: KR101547893B1
Автор: KOO, CHANG HOI, LEE, SHIN YOUNG, PARK, CHAN JUN, JOO, NAM KYU, JO, YOUNG HO
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a method for recovering uranium ion existing in uranium scraps and wasted water generated during a process of manufacturing uranium powder and pellets, and a nuclear fuel pellet using the same. According to the present invention, provided is a method capable of treating uranium existing in the uranium scraps and the wasted water generated during a nuclear fuel manufacturing process efficiently. By providing the nuclear fuel pellet which is manufactured through the uranium treatment process and includes a polyvinyl pyrrolidone-uranium complex capable of performing a role of a pore forming agent and a role of U_3O_8 power at the same time, the method can treat the uranium existing in the uranium scraps and the wasted water generated during the nuclear fuel manufacturing process efficiently and can increase efficient usage of uranium and economic feasibility of nuclear fuel cycle cost together. COPYRIGHT KIPO 2015 (AA) Start (BB) PVP aqueous solution (CC) Forming ...

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Номер записи: 17
24-01-2018 дата публикации

MANUFACTURING METHOD OF URANIUM DIOXIDE FOR NUCLEAR FUEL USING FLUIDIZED BED REACTING APPARATUS

Номер: KR101821617B1
Автор: YANG, SEUNG CHUL, KWAK, DONG YONG, LEE, BYUNG KOOK, CHO, HYUN KWANG, LEE, JUN HO
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present method relates to a fluidized bed reacting apparatus for manufacturing various solid uranium compounds into uranium dioxide (UO_2) for nuclear fuels by calcination and reduction processes, and a manufacturing method of UO_2 using the fluidized bed reacting apparatus. The fluidized bed reacting apparatus of the present invention includes: a fluidized bed reactor (110) in which a uranium compound is filled to produce uranium dioxide by the calcination and reduction processes; a filling chamber (120) to which a fluidizing gas is supplied such that the fluidizing gas is filled therein; an opening and closing valve (130) which is provided in a pipe connecting between the fluidized bed reactor (110) and the filling chamber (120) to perform an opening or closing operation; a controller (140) which controls opening and closing of the opening and closing valve (130); a pressure control unit (150) which controls pressure of the fluidizing gas supplied to the filling chamber (120); and ...

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Номер записи: 18
12-09-2016 дата публикации

METHOD FOR SOLIDIFYING AMMONIA-CONTAINING RADIOACTIVE WASTE

Номер: KR101655416B1
Автор: CHO, NAM CHAN, JU, YOUNG JONG, KIM, JEONG MYEONG, LEE, SEUNG WON, AN, JEONG HAN, HAN, KWANG HO
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD., CHEMICON SYSTEM CO., LTD.

The present invention relates to a method for solidifying ammonia-containing radioactive waste. More specifically, the present invention relates to a method for solidifying ammonia-containing radioactive waste which minimizes environmental pollution and increases satisfactory of a permanent disposal site management standard by extracting and processing the ammonia of ammonia-containing waste while solidifying the waste after liquefying the waste by mixing a fluidization agent with the waste. COPYRIGHT KIPO 2016 (AA) Ammonia waste (BB) Other waste (CC) Waste (less than the standard of ammonia) (DD) Ammonia process (EE) Solidification (S100) Radioactive waste (S200) First mixture (Fluidization agent) (S210) Dry waste? (S220) Adding water (S230) Second mixture (S240) Sampling (S250) Third mixture (Solidification agent) (S260) Packaging (S300) Heating (S400) Ammonia collecting (S500) Waste liquid neutralization (S600) Vapor concentration ...

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Номер записи: 19
15-06-2016 дата публикации

PACKAGE BOX FOR TRANSFERRING HEAVY WATER REACTOR FUEL ASSEMBLY

Номер: KR101630401B1
Автор: KWON, KI JUN, SO, DAL YOUNG, SEOK, CHANG KYU, KANG, SEOK WON, PARK, SUN HO
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a package box for transferring a heavy water reactor fuel assembly. The package box comprises: a rectangular bottom cell (100) which includes a first reception groove portion (110) having at least two columns of reception grooves (111) bent in parallel, and first holding bumps (120) which protrude to be higher than the first reception groove portion (110) and are provided at both end columns of the first reception groove portion (110), wherein the first holding bump (120) is arranged to protrude from an upper portion of the rectangular bottom cell (100) with a step difference with respect to the first reception groove portion (110); a middle cell (200) which is inserted into and assembled with the upper portion of the bottom cell (100), and includes a first fixing groove portion (210) having a fixing groove (211) formed to be bent to correspond to the respective reception grooves of the first reception groove portion (110) at a lower portion of the middle ...

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Номер записи: 20
10-10-2017 дата публикации

STAND FOR HEAT TREATMENT OF MANDREL

Номер: KR101781065B1
Автор: LEE, YOUNG HEE, CHOI, YONG SHIN, KIM, IN KYU, PARK, KI BUM, PARK, MIN YOUNG, JO, SUNG IL, PARK, HWAN JIN
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD., PARK, HWAN JIN

The present invention relates to a stand (10) for heat treatment to not change a form of a mandrel and stably cooling the mandrel when thermally processing and producing the mandrel installed in a lathe, a milling machine, or the like; penetrates a hole on a center of a workpiece; and processes the workpiece. The present invention comprises: a plurality of supports (20) positioned vertically from the ground, and arranged at regular intervals; and a lathe (30) provided with a plurality of plate-shaped plates stacked vertically in a height direction of the support (20) having a plurality of holes (32) with sizes proportional to an installation height. COPYRIGHT KIPO 2017 ...

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Номер записи: 21
08-01-2019 дата публикации

카트리지 필터 세척장치

Номер: KR0101936139B1
Автор: 조남찬, 주영종, 김기태, 엄상용
Принадлежит: 한전원자력연료 주식회사, (주)한국테크

... 본 발명 카트리지 필터 세척장치는 상부가 개폐되고 필터가 투입되는 케이스;와 상기 필터를 지지하며 회동 가능한 회전롤러와, 상기 회전롤러에 동력을 전달하는 제1 동력부가 마련된 고정판;과 상기 필터의 이탈을 방지하는 리프트롤러가 마련되며 상하 이동이 가능한 리프트판;과 상기 리프트판의 하부에 결합되는 회전캠과 상기 회전캠에 편심되게 관통 연결되는 회전축과 상기 회전축에 동력을 전달하는 제2 동력부가 마련되는 캠부;로 구성된다.

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Номер записи: 22
18-01-2016 дата публикации

Jig for heat treatment of a pilger die material

Номер: KR0101585887B1
Автор: 신중철, 김인규, 박기범, 박성희, 이철승
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 필거다이 소재의 열처리에 있어서 필거다이의 둘레면과, 그 나머지 부분에 대해 서로 다른 경도 특성을 갖도록 하기 위한 열처리용 치구에 관한 것으로, 관통 형성된 축공과, 외주 둘레면을 따라서 필거홈이 형성되는 필거다이 소재의 열처리용 치구(100)로서, 상기 필거다이(10)의 두 측면 중 어느 하나와 대응되어 면접촉이 이루어지는 제1플레이트(110)와; 상기 필거다이(10)의 축공(11)에 관통 삽입되어 상기 제1플레이트(110)와 조립이 이루어지는 고정부재(121)가 일체로 마련되어 필거다이(10)의 두 측면 중에서 나머지 하나와 대응되어 면접촉이 이루어지는 제2플레이트(120)와; 상기 제1플레이트(110)에 형성된 최소한 두 개 이상의 볼트 조립공(112)에 각각 삽입되어 상기 고정부재(121)와 나사 조립이 이루어지는 조립볼트(130)로 구성되어, 분해 및 조립이 용이하고 열처리 과정에서 필거다이의 경도 편차 발생을 최소화할 수 있으며, 열처리용 치구의 열변형을 방지하는 효과가 있다.

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Номер записи: 23
29-12-2016 дата публикации

OVERCOATER TO COAT SURFACE OF PARTICLES

Номер: KR101687171B1
Автор: NA, YEON SOO, LIM, GWANG YEONG, LEE, SEUNG JAE, JUNG, TAE SIK, CHOI, MIN YOUNG, MOK, YONG KYOON, KIM, YOON HO, JANG, HUN, LEE, CHUNG YONG, GO, DAE GYUN, LEE, SUNG YONG, KIM, JAE IK
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to an overcoater to coat a coating agent on the surface of ceramic particles. According to the present invention, the overcoater comprises: a housing having an opening part in an upper surface; a rotary shaft vertically inserted into the opening part, and including a hollow lower rotary shaft and an upper rotary shaft inserted into a hallow of the lower rotary shaft to be rotated with the lower rotary shaft; a horizontal rotary unit supported from an inner wall of the housing and horizontally rotating the lower rotary shaft; a vibration unit supported from the inner wall of the housing, and connected to the upper rotary shaft to vertically vibrate the upper rotary shaft; a support bearing unit including a bearing to surround the rotary shaft, and a support fixed on an inner surface of the housing to support the bearing; and a rotary vessel installed at an upper end of the upper rotary shaft. Thus, since a vibration means to vibrate the rotary vessel into which ...

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Номер записи: 24
16-05-2017 дата публикации

핵연료봉 표면 보호를 위한 수용성 코팅제

Номер: KR0101736171B1
Автор: 홍종승, 한상재, 오명호, 공상필, 박성준, 신은우, 신귀인, 이의재, 정근우, 김영운, 이상봉
Принадлежит: 한전원자력연료 주식회사, 한국화학연구원

... 본 발명은 경수로용 핵연료 집합체 제조 시 연료봉 표면에 긁힘(Scratch)를 방지하기 위해 연료봉 표면에 코팅되는 수용성 코팅제에 관한 것이다. 상기와 같은 본 발명에 따르면, 도막의 형성과 제거가 용이하며 형성된 도막의 강도 및 내구성이 기존의 락카(니트로셀룰로스) 도막의 강도 및 내구성과 차이가 없는 정도의 핵연료봉 제조를 위한 수용성 코팅제를 제공하여 기존 락카(니트로셀룰로스)를 대체할 수 있고, 기존 방법에 비하여 도막 제거 공정이 용이하며 작업 안전성 개선으로 근무환경 및 작업 안전성이 놓아지는 효과가 있다.

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Номер записи: 25
11-10-2018 дата публикации

MOVABLE NUCLEAR FUEL ASSEMBLY STRUCTURE DEFORMATION MEASURING APPARATUS

Номер: KR101906854B1
Автор: BAIK, MUN SEOG, KIL, GI BONG, CHANG, KYUNG HUN
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a movable nuclear fuel assembly structure deformation measuring apparatus. More specifically, the movable nuclear fuel collector structure deformation measuring apparatus can measure the length, envelope, and maximum slope of the nuclear fuels to enhance the accuracy in the nuclear fuel assembly structure deformation measurement, be in the shape of a container to have mobility, and enhance the efficiency in measurement location operations. Accordingly, the movable nuclear fuel assembly structure deformation measuring apparatus includes: a container; a powering means and a loading table arranged in the container; a support which is arranged on a side of the loading table of the container and has a hinge means and a fixing means for fixing a nuclear fuel assembly in an upright position; a column which is mounted on the loading table, has a rotary shaft detachably attached to the hinge means installed on an end, and is arranged in an upright position on a side ...

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Номер записи: 26
09-02-2017 дата публикации

전열관 튜브의 외면탈지장치 및 외면탈지방법

Номер: KR0101704642B1
Автор: 김희재, 김득연, 류한옥, 임상현, 김정훈, 신동근, 박준석, 고지훈
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 전열관 튜브의 외면 탈지 장치 및 외면탈지방법에 관한 것으로, 특히 전열관 튜브의 일부만을 감싸는 노즐챔버가 구비되는 전열관 튜브의 외면 탈지 장치에 관한 것으로서, 일정한 길이를 가지는 전열관 튜브의 양단 사이의 일정 구간에서 전열관 튜브의 외주면을 감싸는 격실과, 격실에 설치되어 전열관 튜브에 세척액을 분사하는 노즐로 이루어지는 노즐챔버와, 상기 노즐챔버에 공급되는 세척액이 저장되는 저장탱크 및 상기 저장탱크와 노즐챔버를 연결하는 세척액 공급관으로 이루어져, 전열관 튜브 전체를 탈지액 속에 침지시킬 필요가 없어 대형 탈지수조가 필요 없게 되어 공간과 설비비용이 대폭 절감되고, 대형 탈지수조 방식에 필연적으로 수반되는 여러개의 전열관 튜브를 한꺼번에 운반하는 위험한 작업이 필요없게 되며, 대형 탈지수조로 인한 막대한 탈지액과 세척용수의 낭비가 절감되고, 노즐챔버에 전열관 튜브를 낱개 단위로 투입하여 탈지가 일어나므로 한 명의 작업자가 용이하게 탈지 작업을 수행할 수 있게 되어 인력이 절감되며, 노즐챔버가 튜브의 일부만을 감싸더라도 내부에 탈지액이 채워지므로 기름성분의 이물질이 탈지액에 불려질 수 있고 이와 동시에 전열관 튜브 외면 전체를 훑어내는 솔이 구비됨으로써 물리적인 세척이 함께 일어나 철저한 탈지가 가능한 전열관 튜브의 외면탈지장치를 제공하고자 한다.

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Номер записи: 27
29-08-2016 дата публикации

METHOD TO SYNTHESIZE AXIAL POWER DISTRIBUTION OF REACTOR CORE BY USING NEURAL NETWORK CIRCUIT AND IN-CORE MONITORING SYSTEM APPLYING SAME

Номер: KR101651893B1
Автор: PARK, YOUNG HO, KIM, YOUNG BAEK, KIM, HYE JIN, CHOI, YOUNG JAE, SHIM, KYOUNG WOO
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a method to synthesize an axial power distribution of a reactor core by using a neural network circuit and an in-core monitoring system applying the same. More specifically, the method comprises an input layer, an output layer and one or more hidden layers, and each layer comprises at least one node. Using a neural network circuit formed to make connections between the nodes connected with each connection strength varied according to a learning result while each node is connected to a node of other layers, an optimal connection strength between the nodes forming the neural network circuit through learning based on various core design data applied to a reactor core design of a nuclear power plant is determined, so an axial power distribution of a reactor core is synthesized based on an in-core instrument signal measured through an in-core instrument during operation of a nuclear reactor. Thus, the axial power distribution is more correctly simulated over ...

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Номер записи: 28
27-04-2018 дата публикации

큰 결정립을 갖는 우라늄산화물 핵연료 소결체 조성물의 제조 방법

Номер: KR0101839320B1
Автор: 최민영, 임광영, 이승재, 나연수, 정태식, 김재익, 목용균, 김윤호, 이충용, 장훈, 고대균, 이성용, 유종성
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 첨가제를 함유한 큰 결정립을 갖는 우라늄산화물 핵연료 소결체 조성물과 그 제조방법에 관한 것으로, Mg-화합물과 Si-화합물로 구성된 첨가제 분말과 우라늄산화물 분말이 혼합되어 이루어짐으로써, 결정립 크기가 커서 핵분열 생성물의 방출을 억제할 수 있어서 핵연료의 안정성을 높이고 피복관의 파손을 방지하며 원자로를 안정적으로 운전하는데 기여하여 핵연료를 비롯한 원자로 전체의 안정성을 높일 수 있는 핵연료 소결체를 제공하고자 한다.

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Номер записи: 29
08-06-2017 дата публикации

핵연료집합체용 지지격자의 레이저 용접을 위한 용접치구

Номер: KR0101744346B1
Автор: 오병은, 윤광호, 신동광, 한상재, 홍종승, 홍운수
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 핵연료집합체용 지지격자의 레이저 용접방법에 관한 것으로, 복수의 기준마커가 마련된 용접치구에 의해 가조립되어 레이저 용접이 이루어지는 핵연료집합체용 지지격자의 레이저 용접방법으로서, 상기 기준마커의 위치 좌표를 기준으로 영상정보를 추출하는 제1단계(S10)와; 제1단계(S10)에서 추출된 영상정보에서 기준마커에 대한 위치좌표를 보정하는 제2단계(S20)와; 보정된 기준마커의 위치좌표를 기준으로 용접점에 대한 레이저 용접을 실시하는 제3단계(S30);를 포함한다.

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Номер записи: 30
15-06-2016 дата публикации

Spot welding device for nuclear fuel skeleton and spot welding method using that

Номер: KR0101630405B1
Автор: 김형섭, 국순기, 손세익, 김병탁
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 원자력 연료 골격체를 위한 지지격자에 결합되는 안내관 및 계측관의 용접을 위한 용접장치로서, 판 형상의 프레임에서, 상기 프레임의 두께방향으로 관통되는 연료봉 장입용 셀들이 다수 형성되고 중앙에는 계측관용 삽입공이 형성되며, 계측관용 삽입공을 기준으로 상하 양측에 대칭되게 네 개의 안내관용 삽입공이 형성되는 지지격자에, 출력 제어봉을 위한 안내관과 노내 상태 계측을 위한 계측관이 점용접되어 제조되는 골격체 조립용 용접장치로서, 몸체부와, 몸체부의 일측에서 각각 연장 형성되고 끝단에 각각 구비되는 전극이 서로 대향되는 제1홀더 및 제2홀더와, 몸체부에 구비되는 상기 전극간의 거리 조절용 구동부를 포함하는 용접건과, 상기 용접건에 연결되며 용접건의 상하 반전용 회전관절이 구비되는 로봇을 포함하며, 이때 제1홀더는 몸체부에서의 연장 방향이 절곡되는 경사부를 포함하고, 상기 안내관 사이의 거리(M)는 경사부의 수평 두께(T)보다 더 크며, 제2홀더는 높낮이 차가 발생되는 단차부를 포함하고, 상기 단차부와 상기 경사부 사이의 최단거리(S)는 안내관 단면의 직경(D)보다 더 크도록 되어 기 용접된 안내관이 있더라도 인접되는 안내관 또는 계측관의 용접이 가능하게 되는 골격체 조립용 스폿 용접 장치를 제공하고자 한다.

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Номер записи: 31
22-05-2017 дата публикации

UPPER FIXTURE HAVING ANNULAR PIPE

Номер: KR101738144B1
Автор: KIM, BA LEUM, JEON, SANG YOUN, EOM, KYONG BO, HA, DONG GEUN, KIM, JIN SUN, KIM, SEONG SOO, RYU, JOO YOUNG, KWON, O CHEOL, RYU, SU PIL, CHUN, JOO HONG, NAM, CHAE YOUNG
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to an upper fixture having an annular pipe for seating a flow path plate on an upper portion of a guide pipe. The upper fixture of a nuclear fuel assembly comprises: four inner insertion pipes installed in an upper portion of a nuclear fuel assembly consisting of a plurality of guide pipes, measuring pipes and nuclear fuel rods, which are vertically inserted through a support grid and spaced apart from each other, and screwed to upper portions of the guide pipes; four outer guide parts consisting of outer guide posts surrounding the inner insertion pipes and pressing springs surrounding the outer guide posts; a pressing plate in which first through-holes, into which the outer guide parts are inserted, are formed by the number of the outer guide parts and coupled to upper ends of the outer guide parts to thereby combine the outer guide parts; and a flow path plate which is seated at an upper end of the guide pipe and in which second through-holes, into which ...

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Номер записи: 32
09-11-2016 дата публикации

횡방향 진동을 저감하기 위한 코어핀 홀더캡이 구비된 핵연료 집합체용 상단고정체

Номер: KR0101673876B1
Автор: 김성수, 김재익, 전상윤, 엄경보, 하동근, 김진선, 류주영, 권오철, 류수필, 이학인, 천주홍, 김바름, 남채영
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 핵연료 집합체의 횡방향 진동을 저감하기 위한 코어핀 홀더캡 및, 이를 포함하는 핵연료 집합체용 상단고정체에 관한 것으로, 본 발명의 코어핀 홀더캡은, 핵연료 집합체의 상단고정체 상부에 형성되어 코어핀이 삽입되는 정렬홀에 삽입이 이루어지는 것으로서, 상기 정렬홀(122)에 삽입되어 고정되는 헤드부(131)와; 상기 정렬홀(122)에 대해 수직 방향으로 탄성 변형이 가능하게 상기 헤드부(131)에 마련된 탄성부(132);를 포함한다.

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Номер записи: 33
16-03-2016 дата публикации

ZIRCONIUM ALLOY HAVING EXCELLENT CORROSION RESISTANCE AND CREEP RESISTANCE AND METHOD FOR MANUFACTURING SAME

Номер: KR101604105B1
Автор: CHOI, MIN YOUNG, MOK, YONG KYOON, KIM, YOON HO, NA, YEON SOO, LEE, CHUNG YONG, JUNG, TAE SIK, KO, DAE GYUN, LEE, SEUNG JAE, KIM, JAE IK
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a zirconium alloy having excellent corrosion resistance and creep resistance, and a method for manufacturing the same. The zirconium alloy comprises 1.1-1.2 wt% of niobium, 0.01-0.2 wt% of phosphorous, 0.2-0.3 wt% of iron, and the rest of zirconium. The method for manufacturing a zirconium alloy having excellent corrosion resistance and creep resistance includes: a first step of melting the mixed components of the above zirconium alloy and manufacturing the same into an ingot; a second step of performing a solution heat treatment of the ingot manufactured in the first step for 30-40 minutes at 1,000-1,050 °C (β phase interval), and rapidly cooling to perform the β-Quenching; a third step of preheating the ingot heat-treated in the second step for 20-30 minutes at 630-650°C, and hot-rolling the same at the draft percentage of 60-65%; a fourth step of performing a primary intermediate vacuum heat treatment of the hot-rolled material for 3-4 hours at 570-590 ...

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Номер записи: 34
15-02-2016 дата публикации

Cleaning Technology for Zirconium Scrap Recycling

Номер: KR0101588390B1
Автор: 장흥순, 강종렬, 문종한, 이영희, 안창모, 이덕희, 이지은
Принадлежит: 한전원자력연료 주식회사

... 본 발명에서는 지르코늄 피복관 제조공정에서 발생되는 스크랩을 원전급(Nuclear Grade)으로 재활용하기 위해 스크랩 표면에 부착되어 있는 오염물 제거조건을 최적화하였다. 주 오염물은 피복관 제조시 필거링 공정에서 사용하고 있는 수용성 냉각윤활제 잔류물로서 튜브 표면에 압착 및 탄화된 것으로 가정된다. 스크랩 발생 빈도가 높은 직경 9.50 mm, Zirlo 합금 튜브를 피 세정 대상물로 선정하여 세정 후 피 세정물 표면에 잔존하고 있는 오염물의 특성분석과 피 세정물의 표면 성분분석으로 세정성을 평가하였다. 세정제별 세정능력을 평가하기 위하여 Sodium hydroxide 계열 2종과 Potassium hydroxide 계열 3종을 선정하여 비교하였다. 또한 온도 및 초음파 강도에 따른 세정 효과 분석을 위해 상온, 40℃, 60℃에서 각각 세정한 결과, 세정온도 및 초음파 강도가 높을수록 세정효과도 높은 것으로 나타났다. 육안검사 결과 Sodium hydroxide 계열은 초음파 강도와 무관하게 모두 양호한 것으로 나타났으나 Potassium hydroxide 계열은 초음파 강도 120 W 이상에서 피 세정물의 표면상태가 양호한 것으로 나타났다. 중량측정법에 의한 세정효과 분석결과 Sodium hydroxide 계열은 세정효율이 97.6 %(60 ℃, 120 W)까지 나타났으나 Potassium hydroxide 계열은 피 세정물의 표면상태 불량으로 중량측정 방법을 적용하는 것이 부적합한 것으로 나타났다. 피 세정물의 표면 오염물 분석 결과 C, O, Ca, Zr 성분이 검출되었으며 그 중 C, O의 성분이 대부분을 차지하였음을 알 수 있었다. 피 세정물의 세정 정도에 따라 C, O 구성 비율의 변화가 큰 것으로 나타났으며 세정이 잘될수록 C의 구성비율이 감소되며 상대적으로 O의 구성비율이 증가되었다. 본 발명을 바탕으로 산업현장에 적용하기 위하여 세정공정을 Alkali Cleaning, Rinsing, Drying의 3단계로 구분하고 각 단계별로 세정변수를 ...

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Номер записи: 35
08-06-2017 дата публикации

UPPER FIXER HAVING SELF-ARRANGEMENT STRUCTURE

Номер: KR101744347B1
Автор: RYU, SU PIL, JEON, SANG YOUN, EOM, KYONG BO, HA, DONG GEUN, KIM, JIN SUN, KIM, SEONG SOO, RYU, JOO YOUNG, KWON, O CHEOL, KIM, BA LEUM, CHUN, JOO HONG, NAM, CHAE YOUNG
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to an upper fixer in the upper part of a fuel assembly, having an easy assembly structure. The present invention comprises: four inner insertion pipes installed in the upper part of a fuel assembly, and screwed with a flange of the upper part of a guide pipe; four outer guide parts comprising an outer guide pillar surrounding the inner insertion pipes, and a press spring surrounding the pillar; a press plate combining the outer guide parts by being combined with the upper part of the outer guide parts as first through holes are formed as many as the outer guide parts; and a passage plate including second through holes formed as many as the inner insertion pipes, and a passage in which cooling water flows, placed in the upper part of the guide, and having the lower part of the inner insertion pipes inserted into the second through holes. The inner surface of the flange of the upper part of the guide pipe is smooth to the bottom to become a sliding section in ...

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Номер записи: 36
11-08-2016 дата публикации

지지격자 용접치구 장입장치

Номер: KR0101647019B1
Автор: 오병은, 윤광호, 신동광, 양희섭, 한상재, 홍종승
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 핵연료집합체용 지지격자의 용접치구를 장입하기 위한 장치에 관한 것으로, 베이스프레임(110)과; 상기 베이스프레임(110) 상부에서 용접치구를 수평 이송하게 되는 컨베이어(120)와; 상기 베이스프레임(110) 상부에 설치되어 상기 컨베이어(120)를 따라서 이송된 용접치구를 파지하여 용접챔버 내에 장입하게 되는 그립퍼(200);를 포함하며, 상기 그립퍼(200)는, 그립퍼바디(210)와; 상기 그립퍼바디(210) 선단과 수평하게 설치되어 용접치구를 파지하되, 인가된 수직 하중이 설정 하중 이상에서 상기 그립퍼바디(210)에 대해 수직 방향으로 틸팅이 이루어지는 그립부(220);를 포함한다.

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Номер записи: 37
23-02-2017 дата публикации

원자력발전소 증기발생기 전열관 튜브 탈지 시스템 및 탈지 방법

Номер: KR0101704643B1
Автор: 김희재, 김득연, 류한옥, 임상현, 김정훈, 신동근, 박준석, 고지훈
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 원자력발전소 증기발생기 전열관 튜브 탈지 시스템 및 탈지 방법에 관한 것으로서, 전열관 튜브의 개방된 일측 내부로 세척액을 고속으로 분사시켜 세척하는 내면 탈지부와, 전열관 튜브 외주면의 일부를 감싸는 챔버와, 챔버에 내장되는 세척액 분사 노즐로 이루어져서, 챔버 내부를 통과하는 전열관 튜브의 외주면에 상기 분사 노즐로 탈지액을 분사시키는 외면 탈지부 및, 세척액 저장 탱크와, 세척액 저장 탱크로부터 상기 내면 탈지부 및 외면 탈지부에 세척액을 공급하는 세척액 공급관과, 내면 탈지부 및 외면 탈지부로부터 배출되는 세척액을 세척액 저장 탱크로 회수시키는 세척액 회수관으로 이루어지는 순환부로 이루어짐으로써, 탈지 설비를 위한 대규모 시설이 필요없게 되고, 탈지를 위하여 막대한 양의 탈지액이 소모될 필요가 없게 되며, 여러개의 전열관 튜브를 동시에 탈지하기 위하여 동시에 여러개의 전열간용 튜브를 운반하면서 발생될 수 있는 크고 작은 사고의 위험이 방지되고, 탈지액이 순환됨으로써 하나의 전열관 튜브 탈지를 위한 탈지액으로 다수의 전열관 튜브 탈지가 가능해지게 되어 탈지액과 탈지용수의 소요량이 현저하게 절약 되는 원자력발전소 증기발생기 전열관 튜브 탈지 시스템 및 탈지 방법을 제공하고자 한다.

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Номер записи: 38
21-11-2016 дата публикации

COMPOSITION OF FULLY CERAMIC MICROENCAPSULATED NUCLEAR FUEL CONTAINING TRISTRUCTURAL-ISOTROPIC NUCLEAR PARTICLES HAVING COATING LAYER HAVING HIGHER SHRINKAGE THAN MATRIX, MATERIAL THEREFROM, AND MANUFACTURING METHOD OF SAME

Номер: KR101677175B1
Автор: KIM, YOUNG WOOK, EOM, JUNG HYE, SEO, YU KWANG, LEE, SEUNG JAE
Принадлежит: UNIVERSITY OF SEOUL INDUSTRY COOPERATION FOUNDATION., KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a fully ceramic microencapsulated nuclear material containing tristructural-isotropic nuclear particles coated with ceramic more shrunk than a matrix, in which the tristructural-isotropic nuclear particles before coating are contained within a range of 5-40 volume fraction on the basis of after-sintering. More particularly, composition of fully ceramic microencapsulated nuclear fuel containing tristructural-isotropic nuclear particles coated with a substance mainly containing silicon carbide induced from silicon carbide precursor, a material manufactured therefrom, and a manufacturing method of the material is provided, in which the condition of ΔL_C > ΔL_m upon pressureless sintering is generated when a sintering shrinkage rate of a coating layer of the tristructural-isotropic nuclear particles is ΔL_C, and a sintering shrinkage rate of a silicon carbide matrix is ΔL_m. Remaining void fraction of the fully ceramic microencapsulated nuclear fuel substance ...

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Номер записи: 39
29-12-2017 дата публикации

METHOD OF MEASURING RECRYSTALLIZATION DEGREE OF ZIRCONIUM ALLOY CLAD TUBE FOR NUCLEAR FUEL ROD USING EBSD PATTERN QUALITY

Номер: KR101813624B1
Автор: JUNG TAE SIK, MOK YONG KYOON, KIM YOON HO, LEE CHUNG YONG, JANG HUN
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The purpose of the present invention is to provide a method which is more reliable and accurate when compared to a conventional calculation method as a recrystallization degree of the zirconium clad tube for a nuclear fuel rod is measured in various temperature ranges using pattern quality values measured using electron backscatter diffraction (EBSD). The method comprises: a first step in which electrolytic polishing is performed on a fully recrystallized specimen 1, a partially recrystallized specimen 2 which requires a measurement of the recrystallization degree, and an as-deformed specimen 3, SEM electron beams incident on specimens 1-3 at regular scan intervals, and backscattered electron signals obtained with an EBSD camera; a second step in which the backscattered electron signals obtained from specimens 1-3 are converted to the pattern quality values using EBSD software, and the pattern quality values are calculated as a frequency of a specific range; a third step in which a pattern ...

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Номер записи: 40
11-12-2015 дата публикации

AUTOMATIC FUEL ROD LOADING DEVICE OF NUCLEAR FUEL ASSEMBLY

Номер: KR101575727B1
Автор: NA, TAE HYUNG, HAN, SANG JAE, HONG, JONG SUNG, YANG, KYUNG HWAN
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to an automatic fuel rod loading device to classify and load fuel rods when the fuel rods are completely assembled as a unit component. The automatic fuel rod loading device comprises: a load unit (100) including a plurality of piling units (110) in which a plurality of fuel rods are stacked to be horizontally stored; a loading unit (200) to lift the fuel rods in which the assembly is completed with the unit component according to a barcode marked on each of the fuel rods and to move the fuel rods; an unloading unit (300) to selectively unload a specific fuel rod from among the fuel rods stored in the piling units; a barcode reader (400) to decipher the barcode marked on the surface of the fuel rod that enters the loading unit (200) along a transfer line; a rotary control unit (500) to rotate and drive the fuel rod that enters the loading unit (200) at a constant angle; and a control unit (600) to assort and store the fuel rods in the piling unit (110) by driving ...

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Номер записи: 41
10-04-2018 дата публикации

METHOD AND SYSTEM FOR MONITORING QUALITY OF RESISTANCE WELDING OF LIGHT-WATER REACTOR FUEL ROD BASED ON DISPLACEMENT

Номер: KR101846269B1
Автор: NA, TAE HYUNG, YANG, KYUNG HWAN, HWANG, DONG SOO, KO, MI HYE, CHOI, KYUNG WOO
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD., MONITECH CO., LTD.

The present invention relates to a method and a system for precisely monitoring a quality of resistance welding of an end cap of a light-water reactor fuel rod using a determination factor based on displacement. According to the present invention, the method and the system comprise the following steps of: measuring a welding current (M1), voltage (M2), an instantaneous welding force (IF), and an instantaneous displacement (ID); calculating to primarily evaluate an instantaneous dynamic resistance (IDR), an instantaneous heating rate (IHR), a whole average dynamic resistance (M3), and a whole average heating amount (M4); and providing state information after going through final evaluation in accordance with whether or not a value of each of from BW0 to BW6 of the detailed determination factor is within a predetermined reference value range. COPYRIGHT KIPO 2018 (AA) End (s10) Measuring step (s20) Instantaneous resistance calculation step (s21) Instantaneous heating rate calculation step ( ...

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Номер записи: 42
04-05-2017 дата публикации

SPACER GRID HAVING SPRING STRUCTURE WITH OPENED ONE SIDE

Номер: KR101732174B1
Автор: NAM, CHAE YOUNG, JEON, SANG YOUN, EOM, KYONG BO, HA, DONG GEUN, KIM, JIN SUN, KIM, SEONG SOO, RYU, JOO YOUNG, KWON, O CHEOL, RYU, SU PIL, CHUN, JOO HONG, KIM, BA LEUM
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a spacer grid having a spring structure with opened one side, having low spring stiffness at the time of charging a fuel rod and capable of realizing high spring stiffness during operation. A spacer grid for a nuclear fuel assembly comprises a plurality of grid plates (100) intersecting in a lattice form and having a grid spring for supporting a fuel rod which is disposed in a partitioned cell, wherein the grid spring (110) comprises: a fuel rod contact portion (111) for supporting the fuel rod in a longitudinal direction; a fixed end (112a) extending from one side of the fuel rod contact portion (111) and fixed to the grid plate (100) in the longitudinal direction; and a free end (113a) extending from the other side of the fuel rod contact portion (111) and elastically touching the grid plate (100). COPYRIGHT KIPO 2017 ...

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Номер записи: 43
08-02-2018 дата публикации

LOWER FIXING BODY OF NUCLEAR FUEL ASSEMBLY HAVING INSERTABLE FOREIGN MATERIAL FILTRATION DEVICE

Номер: KR101826045B1
Автор: KIM, JIN SUN, KIM, BA LEUM, KIM, SEONG SOO, PARK, NAM GYU, YOO, JONG SUNG
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a lower fixing body of a nuclear fuel assembly having an insertable foreign material filtration device which prevents foreign materials in a flow hole formed in a lower fixing body. The lower fixing body comprises: a base which comprises a flow plate having a plurality of flow holes, and lower legs integrally formed on the bottom surface of the flow plate to support the flow plate; and an insertable filtration unit which has a plurality of inserting ports which are a member formed in a shape corresponding to an inner circumferential surface of the flow hole, are inserted into the bottom surface of the flow hole, and are inserted into the flow hole to be separated from the inner circumferential surface of the flow hole by a predetermined width, such that cooling water rises through a separated space by the predetermined width, and foreign materials contained in the cooling water remain in the bottom surface of the base, thereby filtering foreign materials ...

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Номер записи: 44
07-12-2016 дата публикации

TOP FIXTURE HAVING SLIDING-TYPE PUSH SPRING

Номер: KR101679607B1
Автор: CHUN, JOO HONG, JEON, SANG YOUN, EOM, KYONG BO, HA, DONG GEUN, KIM, JIN SUN, KIM, SEONG SOO, RYU, JOO YOUNG, KWON, O CHEOL, RYU, SU PIL, KIM, BA LEUM, NAM, CHAE YOUNG
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a top fixture having a push spring particularly varied in a sliding type. The top fixture comprises: a coupling plate which has a lower portion to which a guide pipe is fixed; a surrounding plate which is formed to protrude upwards along the edge of the coupling plate; and a plurality of push springs which are provided on the upper surface of the surrounding plate, wherein the push springs include a first spring which is formed by bending both ends of one elastic member, and a second spring which has the same shape as that of the first spring, is smaller than that, and is disposed between both ends of the first spring, a guide means is formed on the upper surface of the surrounding plate along the length direction of the surrounding plate, both ends of the first spring and the second spring are inserted to the guide means to be sliding-variable, there is no interference between springs, it is possible to embody an accurate spring operation time point by ...

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Номер записи: 45
17-05-2017 дата публикации

PULSE COLUMN HAVING PULSE SUPPLY APPARATUS

Номер: KR101736168B1
Автор: BAE, YOUNG MOON, YANG, SEUNG CHUL, LEE, BYUNG KUK, KWAK, DONG YONG, CHO, HYUN KWANG
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a pulse supply apparatus and a pulse supply method for a pulse column used for a solvent extraction process, and more specifically, a pulse supply apparatus which can be economically and conveniently installed on an extraction tower or pulse column used as unit equipment for a solvent extraction process to reliably supply pulses to the pulse column. According to an embodiment of the present invention, the pulse supply apparatus is a pulse supply apparatus for a pulse column (10) for a solvent extraction process, which is driven by electricity or pressurized air, and in which one of an outlet (42) and a suction part (44) is blinded while the other one of the outlet (42) and the suction part (44) includes a diaphragm pump (20) connected to the pulse column (10) by a pulse supply line (40), wherein the pulse column (10) has a first solvent inlet (52) and a second solvent outlet (58) provided at a lower column unit, and a second solvent inlet (56) and a first ...

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Номер записи: 46
11-10-2018 дата публикации

STANDARD OF MOVABLE NUCLEAR FUEL ASSEMBLY STRUCTURE DEFORMATION MEASURING APPARATUS

Номер: KR101906855B1
Автор: BAIK, MUN SEOG, KIL, GI BONG, CHANG, KYUNG HUN
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a standard of a movable nuclear fuel assembly structure deformation measuring apparatus. More specifically, the standard of a movable nuclear fuel assembly structure deformation measuring apparatus can have standard objects corresponding to the standard specifications of a nuclear fuel assembly to execute a scanner correction operation for enhancing the measurement accuracy of a scanner for measuring the nuclear fuel assembly. Accordingly, the movable nuclear fuel assembly structure deformation measuring apparatus in the shape of a container storing a measurement apparatus includes: a fixing frame which is fixed to a side of the measurement apparatus stored in the container; and standard objects which rotate around an end of the fixing frame while being attached to and detached from the fixing frame as well as corresponding to the standard specifications of the nuclear fuel assembly. An upper plate having a coupling means coupled to a conveying apparatus ...

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Номер записи: 47
01-09-2016 дата публикации

RADIOACTIVELY POLLUTED SOIL DECONTAMINATION SYSTEM

Номер: KR101652811B1
Автор: CHO, NAM CHAN, SEOL, JEUNG GUN, JU, YOUNG JONG, KANG, HYUN GYU
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a radioactively polluted soil decontamination system. More specifically, the present invention relates to a radioactively polluted soil decontamination system which separates a pebble and an organic material through a mesh and a blower, and only separates fine soil with high radioactive pollution, thereby increasing decontamination efficiency and a reduction rate of soil for reuse. COPYRIGHT KIPO 2016 (AA) Ton bag ...

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Номер записи: 48
21-07-2016 дата публикации

SOLIDIFICATION AGENT TO SOLIDIFY RADIOACTIVE WASTE INCLUDING ALUMINA CEMENT AND METHOD TO SOLIDIFY RADIOACTIVE WASTE USING SAME

Номер: KR101641281B1
Автор: CHO, NAM CHAN, JU, YOUNG JONG, KIM, JEONG MYEONG, LIM, DONG HAN, KI, KYOUNG KUK, PARK, JUNG HOON
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD., CHEMICON CO., LTD.

The present invention relates to a solidification agent to solidify a radioactive waste. The solidification agent to solidify radioactive waste comprises an alumina cement and a plaster powder. According to the present invention such as this, the solidification agent including alumina cement and plaster powder is provided; thereby in solidifying radioactive waste, an increase in a volume of the solidification agent of the radioactive waste is able to be minimized at a level which satisfies a chemical safety regulation. As such, the radioactive waste is able to safely be solidified. COPYRIGHT KIPO 2016 ...

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Номер записи: 49
18-08-2016 дата публикации

METHOD OF RECOVERING URANIUM BY TREATMENT PROCESS OF WASHING WASTEWATER PRODUCED FROM WASHING PROCESS OF URANIUM HEXAFLUORIDE CYLINDER

Номер: KR101648973B1
Автор: BAE, YOUNG MOON, SHIN, HYUN DONG, YANG, SEUNG CHUL, JO, BO HYUN, LEE, BYUNG KUK, KWAK, DONG YONG, CHO, HYUN KWANG, GU, SUNG HOI, HWANG, EUI JUN
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a method of recovering uranium by a treatment process of washing wastewater produced from a washing process of a uranium hexafluoride cylinder. According to the present invention, uranium (U) is separated from waste water produced during a washing process of a uranium hexafluoride cylinder (UF6), and a filtrate of the wastewater is vaporized and condensed. By the vaporization and condensation, the filtrate may satisfy a limit of atomic licensing and a limit of an environmental licensing such that the filtrate may be discharged. The invention has a benefit of securing a unique technique and a process to treat waste water produced from a washing process of the uranium hexafluoride cylinder, performing maintenance more easily with a unique technique, and save large amount of costs as there is no need to purchase facilities from foreign companies. COPYRIGHT KIPO 2016 (AA) Wastewater storage room (BB) CO3 discharge (CC) First storage tank for liquid waste (COLUMN ...

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Номер записи: 50
03-03-2017 дата публикации

전열관 튜브의 내면탈지장치 및 내면탈지방법

Номер: KR0101711550B1
Автор: 김희재, 김득연, 류한옥, 임상현, 김정훈, 신동근, 박준석, 고지훈
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 전열관 튜브의 내면탈지장치 및 내면탈지방법에 관한 것으로, 특히 전열관 튜브 내면에 ??지액과 버블을 분사하여 탈지시키는 탈지장치 및 탈지방법에 관한 것으로서, 전열관 튜브의 개방된 일측으로 세척액과 공기를 동시에 불어넣는 버블생성노즐과, 상기 버블생성노즐에 세척액을 공급하는 세척액 저장 탱크와, 상기 세척액 저장 탱크와 버블생성노즐을 연결시키는 세척액 공급관 및 상기 버블생성노즐에 압축공기를 공급하는 공기압축기로 이루어져서, 버블생성노즐이 전열관 튜브의 일단에만 결합되어도 하나의 전열관 튜브 전체의 내면 및 외면 탈지가 가능하므로, 전열관 튜브가 하나씩 차례로 투입되어 낱개 단위로 세척 가능하게 되어 대형 수조에 대량의 탈지액을 받아서 여러개의 튜브를 동시에 탈지시킬 필요가 없게 되어 1) 탈지 설비를 위한 대규모 시설이 필요없게 되고, 2) 탈지를 위하여 막대한 양의 탈지액이 소모될 필요가 없게 되며, 3) 여러개의 전열관 튜브를 동시에 탈지하기 위하여 동시에 여러개의 전열간용 튜브를 운반하면서 발생될 수 있는 크고 작은 사고의 위험이 방지되고, 탈지액이 순환됨으로써 하나의 전열관 튜브 탈지를 위한 탈지액으로 다수의 전열관 튜브 탈지가 가능해지게 되어 탈지액과 탈지용수의 소요량이 현저하게 절약될 수 있는 전열관 튜브의 내면탈지장치 및 내면탈지방법을 제공하고자 한다.

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Номер записи: 51
06-10-2015 дата публикации

METHOD FOR MANUFACTURING POLYVINYL PYRROLIDONE-ALUMINIUM COMPLEX AND NUCLEAR FUEL PELLET

Номер: KR101557397B1
Автор: KOO, CHANG HOI, LEE, SHIN YOUNG, PARK, CHAN JUN, JOO, NAM KYU, JO, YOUNG HO
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a method for manufacturing a polyvinyl pyrrolidone-aluminum (polyvinyl pyrrolidone-Al) complex which is an additive capable of growing the size of a pore and a grain at the same time, and a nuclear fuel pellet manufactured by adding the polyvinyl pyrrolidone-Al complex. According to the present invention, the polyvinyl pyrrolidone-Al complex and the nuclear fuel pellet using the same are provided, thereby minimizing a densification phenomenon that volume is decreased in a furnace at the initiatory stage, and volumetric expansion that volume is increased when reaching a certain degree of combustion. Accordingly, the present invention contributes to the use of a high combustion and long-period nuclear fuel, thereby effectively utilizing uranium and increasing economic efficiency of nuclear fuel cycle costs. COPYRIGHT KIPO 2016 (AA) Start (BB) PVP solution (CC) Forming a PVP-AI(III) complex (DD) Filtering the PVP-AI(III) complex (EE) Drying the PVP-AI(III) ...

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Номер записи: 52
11-05-2018 дата публикации

METHOD AND APPARATUS FOR TREATING RESIDUES IN URANIUM HEXAFLUORIDE CYLINDER THROUGH GAS PHASE REACTION

Номер: KR101856467B1
Автор: BAE, YOUNG MOON, MOON, YU DON, HWANG, IN KYU, SHIN, HYUN DONG, YANG, SEUNG CHUL, KWAK, DONG YONG, LEE, BYUNG KOOK, CHO, HYUN KWANG, LEE, JUN HO
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a method and an apparatus for treating residues in uranium hexafluoride cylinder (UF_6 heel) through a gas phase reaction. Particularly, the treating method includes the steps of: (1) vaporizing a UF_6 heel; (2) generating UO_2F_2 in solid phase by using a vaporized UF_6 gas; (3) separating the solid-phase UO_2F_2 from a by-product gas; and (4) separating hydrogen fluoride in the by-product gas. The treating apparatus includes: (1) a dedicated vaporizer for vaporizing a UF_6 heel; (2) a reactor connected to the vaporizer to generate UO_2F_2 by using a UF_6 gas generated in the vaporizer; (3) a solid·gas phase separator connected to the reactor to separate a solid-phase UO_2F_2 generated in the reactor from a by-product gas; (4) a heat exchanger connected to the solid·gas phase separator and allows the by-product gas supplied from the solid·gas phase separator to pass therethrough to condense a liquid; and (5) a liquid·gas phase separator for separating liquid ...

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Номер записи: 53
08-05-2017 дата публикации

FUEL PALLET VISUAL INSPECTION DEVICE FOR MANUFACTURING NUCLEAR FUEL ROD

Номер: KR101732884B1
Автор: NA, TAE HYUNG, KOH, HAN KYUL
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a fuel pallet visual inspection device for manufacturing a nuclear fuel rod. The invention relates to a frame, comprising: a frame including a base plate and a side cover plate; a rotary shaft disposed on one side with respect to the center of the base plate; a pair of mounting plates hinge-coupled to the rotary shaft and disposed on both sides of the rotary shaft, respectively, with respect to the rotary shaft; and a dust collecting unit in which dust scattered from the pallet is collected. The present invention facilitates visual inspection of the pallet through tray inversion in which the pallet is aligned. COPYRIGHT KIPO 2017 ...

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Номер записи: 54
11-08-2016 дата публикации

핵연료집합체의 지지격자용 비드 블라스터

Номер: KR0101647015B1
Автор: 김항래, 오병은, 윤광호, 신동광, 홍종승, 한상재
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 핵연료집합체의 지지격자 제조공정 중에서 지지격자 외부면을 비드 블라스팅 가공하기 위한 지지격자용 비드 블라스터에 관한 것으로, 기밀부재에 의해 기밀이 이루어져 개폐 가능한 도어가 마련된 작업챔버(110)와; 상기 작업챔버 내에 마련되어 다수 개로 적층된 지지격자가 안착 위치하여 회전 가능한 인덱스 테이블(120)과; 상기 인덱스 테이블(120)을 회전 구동시키기 위한 제1구동부(130)와; 상기 작업챔버(140) 내에서 상기 인덱스 테이블과 인접하여 마련된 노즐부(140)와; 상기 작업챔버(110)의 바깥에 배치되어 상기 노즐부(140)와 구동암(151)으로 연결되어 상기 노즐부(140)의 위치를 조정하게 되는 제2구동부(150)와; 압축공기를 발생시키는 콤퓨레서(160)와; 비드가 저장되어 상기 콤퓨레서(160)에서 공급된 압축공기에 의해 비드가 혼합된 압축공기를 상기 노즐부(140)를 통해 분사하게 되는 비드 저장부(170)와; 상기 작업챔버(110) 하부와 연결되어 혼합공기 중의 비드를 여과하여 상기 비드 저장부(160)로 비드를 전달하게 되는 사이클론(180)과; 상기 사이클론(170)과 연결되어 혼합공기 중의 분진을 여과하기 위한 집진장치(190)와; 상기 제1구동부(130)와 제2구동부(150)의 구동을 제어하며, 상기 콤퓨레서(160)를 제어하여 상기 노즐부(140)를 통해 분사되는 분사압을 조정하게 되는 제어부(200);를 포함한다.

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Номер записи: 55
28-11-2016 дата публикации

지지격자의 레이저 용접장치

Номер: KR0101679606B1
Автор: 신동광, 오병은, 윤광호, 한상재, 홍종승, 차광석, 홍운수
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 핵연료집합체용 지지격자의 레이저 용접장치에 관한 것으로, 중앙에 수평하게 챔버설치구가 관통 형성되고, 그 챔버설치구를 따라서 가이드레일(110)이 설치되는 베이스프레임(100)과; 상기 가이드레일(110)에 의해 안내되어 상기 베이스프레임(100)과 조립되며, 전방에 개폐 가능한 도어(210)가 마련되고 상부에 글라스윈도우(220)가 구비되어 기밀이 이루어지는 용접챔버부(200)와; 상기 베이스프레임(100)에 설치되어 상기 글라스윈도우(220)를 통해 레이저를 조사하여 용접챔버부(200) 내의 지지격자를 용접하게 되는 레이저용접부(300)와; 상기 용접챔버부(200)를 상기 베이스프레임(100)에 고정하기 위한 록킹부재(410);를 포함한다.

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Номер записи: 56
08-03-2018 дата публикации

원자력 발전소의 노심설계 자동 검증 시스템

Номер: KR0101836333B1
Автор: 유상근, 김대호
Принадлежит: 한전원자력연료 주식회사

... 본 기술은 원자력 발전소의 노심설계 자동 검증 시스템 및 방법을 개시한다. 본 기술의 구현 예에 따르면, 원자력 발전소의 노심설계 시에 설계 결과물을 신속 정확하게 자동검증 함으로써 설계품질을 제고할 수 있으며, 검증된 설계값은 자동으로 데이터베이스에 저장됨에 따라 체계적 관리가 가능하여 경험있는 설계자의 노하우를 빠짐없이 보존하여 전수할 수 있다. 설계에 우호적이지 않은 급박한 설계환경 시에도 최소한의 설계품질을 확보하여 원자력 발전소의 안전에 기여할 수 있다.

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Номер записи: 57
26-09-2017 дата публикации

MODULE TYPE EXTRACTION COLUMN

Номер: KR101777228B1
Автор: BAE, YOUNG MOON, YANG, SEUNG CHUL, LEE, BYUNG KUK, KWAK, DONG YONG, MIN, JUN SANG
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a module type extraction column (1), as a modulated extraction column, which is simply maintained by being easily manufactured and installed, and by changing a process or a structure inside the extraction column after installation, replacing damaged structures, removing contaminants, and the like, wherein the extraction column comprises: a head block (10) having a flange (110) on one side; a body block (20) assembled by being laminated with the flange (110), having a first module flange (212) and a second module flange (213) provided on both sides of the flange (110) in the same axis with different direction, and having a column body module, (210) having a receiving part (211) of a predetermined area formed therein, which is coupled to the first module flange (212) and the second module flange (213) to each other; and an inner structure (30) provided in the receiving part (211) to disperse a fluid, wherein the head block (10) and the body block (20) are ...

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Номер записи: 58
07-10-2015 дата публикации

MANUFACTURING METHOD OF ZIRCONIUM ALLOYS HAVING EXCELLENT LOW-HYDROGEN ABSORPTION AND HYDROGEN EMBRITTLEMENT RESISTANCE, AND ZIRCONIUM ALLOY COMPOSITIONS HAVING SAME

Номер: KR101557391B1
Автор: NA, YEON SOO, MOK, YONG KYOON, KIM, YOON HO, LEE, CHUNG YONG, CHOI, MIN YOUNG, JUNG, TAE SIK, SHIN, JUNG HO, LEE, SEUNG JAE, SUH, JUNG MIN
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to zirconium alloy compositions having excellent low-hydrogen absorption and hydrogen embrittlement resistance, and a manufacturing method thereof. More specifically, the present invention relates to the zirconium alloy compositions comprising: (1) 1.0-1.4 wt% of Nb, 0.1-0.3 wt% of Sc, 0.04-0.06 wt% of Al, 0.1-0.3 wt% of Sn, 0.04-0.06 wt% of Fe, and a remainder of Zr; (2) 1.0-1.4 wt% of Nb, 0.1-0.3 wt% of Sc, 0.04-0.06 wt% of Al, 0.04-0.08 wt% of Cu, and a remainder of Zr; (3) 1.2-1.4 wt% of Nb, 0.1-0.3 wt% of Sc, 0.04-0.06 wt% of Al, 0.1-0.3 wt% of Cr, and a remainder of Zr. According to the present invention, the zirconium alloy compositions are properly controlled for a type of added element, dosage and heat processing temperature, and the like, to improve a low-hydrogen absorption and hydrogen embrittlement resistance; thereby delivering excellent low-hydrogen absorption and hydrogen embrittlement resistance when compared with a conventional zircaloy-4 ...

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Номер записи: 59
23-06-2016 дата публикации

Nuclear fuel assembly top nozzle having a structure of inserting an ICI utilizing an upper core plate pin

Номер: KR0101632182B1
Автор: 김성수, 김재익, 전상윤, 엄경보, 하동근, 김진선, 류주영, 권오철, 류수필, 이학인, 천주홍, 김바름
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 상부노심판 가이드핀을 이용하여 원자로 상부헤드 관통형 노내계측기가 삽입되는 상단고정체 및 원자로에 관한 것으로, 핵연료 집합체의 상단고정체와 원자로의 상부노심판을 정렬하는 가이드핀을 포함하는 원자로에 있어서, 상기 가이드핀(200)의 축방향으로 관통 형성된 가이드공(210)이 형성되며, 상기 가이드공(210)을 따라서 노내계측기(10)가 삽입되는 것을 특징으로 한다.

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Номер записи: 60
05-06-2018 дата публикации

BOTTOM FIXTURE FOR NUCLEAR FUEL ASSEMBLY WITH FOREIGN MATERIAL FILTERING DEVICE FORMED THEREIN

Номер: KR101851181B1
Автор: KIM, BA LEUM, KIM, SEONG SOO, RYU, SU PIL, PARK, NAM GYU, YOO, JONG SUNG
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a bottom fixture for a nuclear fuel assembly and, more specifically, to a bottom fixture for a nuclear fuel assembly with a foreign material filtering device formed therein, which includes a foreign material filtering device between flow path holes in order to improve foreign material filtering performance and enhance cooling water distribution effects thereof. In addition, the bottom fixture for a nuclear fuel assembly with a foreign material filtering device formed therein comprises: a plate (110) which is formed on the top surface thereof; a plurality of flow path holes (120) which are formed on the plate (110), and of which at least a portion is formed by being divided by a plurality of horizontal elements (112) and vertical elements (114) at right angles to the horizontal elements (112); a connection hole (130) which is formed at an area where the horizontal element (112) and the vertical element (114) meet; and a plurality of wings (140) which are ...

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Номер записи: 61
15-11-2017 дата публикации

핵연료봉 저항용접 품질 모니터링 방법

Номер: KR0101798110B1
Автор: 나태형, 황동수, 고미혜, 최경우
Принадлежит: 한전원자력연료 주식회사, 모니텍(주)

... 본 발명은 핵연료봉 저항용접 품질 모니터링 방법에 관한 것으로, 특히 피복관과 봉단마개의 가압 저항용접 품질을 실시간으로 모니터링할 수 있는 방법에 관한 것으로, 피복관과 봉단마개의 가압 저항용접 과정에서 전압, 전류 및 가압력을 포함한 용접정보를 검출하는 제1단계(S10)와; 용접정보들에 대한 각 실효값을 산출하여 얻은 정적인자를 각각의 설정 기준값과 비교 판정하는 제2단계(S20)와; 제2단계(S20)에서 설정 기준값 범위를 만족하면, 순시가압력 기울기를 포함한 용접정보에 대한 동적인자를 산출하는 제3단계(S30)와; 상기 동적인자를 비교 판정하여 용접품질의 불량 여부를 판정하는 제4단계(S40);를 포함한다.

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Номер записи: 62
29-11-2018 дата публикации

핵연료봉 제조용 용접장치

Номер: KR0101923394B1
Автор: 양경환, 조영춘
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 핵연료봉 제조용 용접장치에 관한 것으로, 특히 봉단마개와 피복관을 용접하는 과정에서 용접 비드(weld bead) 발생을 방지하여 용접 공정 이후에 용접부에 대한 연삭 공정을 배제할 수 있는 핵연료봉 제조용 용접장치에 관한 것으로, 피복관(110)이 삽입 위치하도록 관통 형성된 관통홀이 형성된 튜브전극(210)과, 상기 피복관(110) 일단과 용접 고정이 이루어지는 봉단마개(120)를 고정하는 마개전극(220)을 포함하여 피복관(110)과 봉단마개(120)를 용접하기 위한 용접장치에 있어서, 상기 튜브전극(210)은 상기 관통홀을 감싸도록 몸체(211)의 표면 일부에 절연체(212)가 마련되며, 상기 절연체(212)는 개구부에 상기 관통홀보다 큰 직경을 가지며 인입 형성된 스텝(S)을 포함하여, 튜브전극과 봉단마개 사이의 미세한 갭(gap) 설정으로 인하여 아크 또는 누설전류로 발생할 수 있는 핵연료봉의 용접 품성 저하를 방지할 수 있다.

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Номер записи: 63
25-03-2016 дата публикации

ZIRCONIUM ALLOY FOR NUCLEAR FUEL PIPE HAVING EXCELLENT CORROSION RESISTANCE AND FABRICATION METHOD THEREOF

Номер: KR101604103B1
Автор: CHOI, MIN YOUNG, MOK, YONG KYOON, KIM, YOON HO, NA, YEON SOO, LEE, CHUNG YONG, JANG, HUN, JUNG, TAE SIK, KO, DAE GYUN, LEE, SUNG YONG, LEE, SEUNG JAE, KIM, JAE IK
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

Provided are a zirconium alloy for a nuclear fuel pipe having excellent corrosion resistance, which is used for a nuclear fuel pipe, a structural member, etc. by completely removing tin with a bad influence on corrosion-resistance, and a fabrication method thereof. The zirconium alloy for a nuclear fuel pipe, according to the present invention, comprises: 0.5-1.2 wt% of Nb, 0.4-0.8 wt% of Mo, 0.1-0.15 wt% of Cu, 0.15-0.2 wt% of Fe, and the remainder consisting of Zr. COPYRIGHT KIPO 2016 (AA) Alloy dissolution (BB) β - solution heat treatment and quenching (CC) Hot rolling (Reduction ratio: 60~65%), preheating 630~650°C, 20 minutes (DD) Primary middle heat treatment (580~590°C, three to four hours) (EE) Primary cold rolling (Reduction ratio: 30 to 40 %) (FF) Secondary middle heat treatment (570~580°C, two to three hours) (GG) Secondary cold rolling (Reduction ratio: 50 to 60%) (HH) Tertiary middle heat treatment (570~580°C, two to three hours) (II) Tertiary cold rolling (Reduction ratio: ...

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Номер записи: 64
05-06-2018 дата публикации

BOTTOM FIXTURE FOR NUCLEAR FUEL ASSEMBLY FOR PROVIDING IMPROVED FOREIGN MATERIAL FILTERING PERFORMANCE

Номер: KR101851184B1
Автор: KIM, BA LEUM, KIM, SEONG SOO, NAM, CHAE YOUNG, PARK, NAM GYU, YOO, JONG SUNG
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a bottom fixture for a nuclear fuel assembly, and more particularly, to a bottom fixture for a nuclear fuel assembly for providing improved foreign material filtering performance, including a propeller type filtering unit between flow holes formed in the bottom fixture in order to increase a cooling water distribution effect and to improve the foreign material filtering performance of the bottom fixture for a nuclear fuel assembly. The bottom fixture for a nuclear fuel assembly for providing improved foreign material filtering performance according to the present invention includes: a plate (110) on which a plurality of flow holes (120) for the flow of cooling water are formed; and the propeller type filtering unit formed in at least some of the plurality of flow holes (120). COPYRIGHT KIPO 2018 ...

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Номер записи: 65
08-02-2019 дата публикации

드럼 절단 시스템

Номер: KR0101945455B1
Автор: 설증군, 류지창, 황철현
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 드럼 절단 시스템에 관한 것으로서, 보다 구체적으로는, 드럼의 효과적인 제염을 위하여 드럼의 하부면 테두리 부분을 절단 및 분리하도록 구성되는 드럼 절단 시스템에 관한 것이다. 본 발명에 따른 드럼 절단 시스템은, 드럼을 고정 장착하기 위한 고정부; 상기 고정부를 회전시키기 위한 회전부; 및 상기 고정부의 일측에 형성되고, 드럼의 절삭을 위한 절삭부;를 포함할 수 있다.

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Номер записи: 66
14-06-2017 дата публикации

UPPER FIXER HAVING HORIZONTAL ROTATION STRUCTURE

Номер: KR101746780B1
Автор: RYU, SU PIL, JEON, SANG YOUN, EOM, KYONG BO, HA, DONG GEUN, KIM, JIN SUN, KIM, SEONG SOO, RYU, JOO YOUNG, KWON, O CHEOL, KIM, BA LEUM, CHUN, JOO HONG, NAM, CHAE YOUNG
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to an upper fixer having a ring-shaped tube to place a passage panel in the upper part of a guide tube for a fuel assembly. The upper fixer comprises: four internal insertion tubes installed in the upper part of a fuel assembly comprising a plurality of measurement and guide tubes and a fuel rod, and screwed with a flange of the guide tubes; four edge guide parts comprising an edge guide pillar surrounding the internal insertion tubes and a press spring surrounding the edge guide pillar; a pressing panel including first through holes, penetrated by the edge guide parts with as many formed as the number of the edge guide parts, to be combined with the upper part of the edge guide parts; and a passage panel including second through holes, penetrated by the internal insertion tubes with as many formed as the number of the internal insertion tubes, and a passage, in which cooling water flows, placed in the upper part of the guide tubes, and having the lower part ...

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Номер записи: 67
14-09-2015 дата публикации

GAP ADJUSTMENT DEVICE FOR PILGER DIE ASSEMBLY OF COLD-PILGER ROLLING MILL

Номер: KR101552514B1
Автор: SHIN, JUNG CHEOL, KIM, IN KYU, PARK, KI BUM, CHOI, YONG SHIN, HWANG, HO YEON
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a gap adjustment device capable of independently adjusting a height of a pair of bearing blocks to support an upper die in a pilger die assembly of a cold-pilger rolling mill. The gap adjustment device comprises: a lower plate (110) having first and second placing holes (111, 112) penetrated in response to the upper part of the bearing blocks to support the upper die to be rotated; first and second wedge plates (120, 130) inserted in the first and second placing holes (111, 112), and having an inclined surface on the upper part; first and second adjustment blocks (140, 150) having a guide inclined surface being in surface contact with the inclined surface of the first and second wedge plates (120, 130) to horizontally move with respect to the lower plate (110); an upper plate (160) assembled to the upper part of the lower plate (110) to cover the upper part of the first and second adjustment blocks (140, 150); and first and second adjustment bolts (170, ...

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Номер записи: 68
04-05-2017 дата публикации

혼합날개 없이 믹싱효과를 갖는 지지격자

Номер: KR0101732173B1
Автор: 류주영, 전상윤, 엄경보, 하동근, 김진선, 김성수, 권오철, 류수필, 천주홍, 김바름, 남채영
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 별도의 혼합날개를 배제하고 격자스프링 구조만을 이용하여 믹싱효과를 얻을 수 있는 지지격자에 관한 것으로, 격자 형태로 교차되어 구획된 셀 내에 배치되는 연료봉을 지지하게 되는 격자스프링을 갖는 다수의 격자판을 포함하는 핵연료 집합체의 지지격자에 있어서, 상기 격자스프링은, 상기 격자판(110)에 관통 형성된 원도우(111)를 종방향으로 가로지르도록 상단과 하단에 각각 마련되는 제1탄성부재(120)와 제2탄성부재(130)를 포함하되, 상기 제1탄성부재(120)와 상기 제2탄성부재(130)는 종방향에 대해 서로 다른 편각을 갖고 상기 격자판(110)을 기준으로 서로 반대편에서 나란하도록 상기 격자판(110)에서 절곡되어 연장 형성된 한 쌍의 탄성플레이트(122)(124);를 포함한다.

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Номер записи: 69
22-04-2016 дата публикации

METHOD OF SYNTHESIZING AXIAL POWER DISTRIBUTION OF REACTOR CORE USING NEURAL NETWORK AND IN-CORE PROTECTION SYSTEM APPLYING SAME

Номер: KR101614772B1
Автор: PARK, YOUNG HO, KIM, YOUNG BAEK, KIM, DONG SOO, OH, DO YOUNG
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to a method of synthesizing an axial power distribution of a reactor core using a neural network and an in-core protection system (ICOPS) applying the same. More specifically, the neural network comprises an input layer, an output layer, and one or more hidden layers. Each layer comprises at least one node and each node is connected to nodes of other layers, while the connection between the nodes is made with each of variable connection strengths based on a learning result. The optimal connection strength between the nodes composing the neural network is determined through learning that is based on various reactor core design data applied to the reactor core design of a nuclear power plant, so that the axial power distribution of the reactor core can be synthesized, based on ex-core neutron flux detector signal measured by an ex-core neutron flux detector while the reactor is operated. As a result, there is no need for an extra measurement of basic data to ...

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Номер записи: 70
28-05-2018 дата публикации

압력보상형 하중전달장치

Номер: KR0101861568B1
Автор: 김경홍, 김진선, 유종성, 전경락, 엄경보, 박준규, 유영익, 권오준, 김중진, 이태권
Принадлежит: 한전원자력연료 주식회사

... 본 발명에 따른 압력보상형 하중 전달장치(1)는, 일측면에 제1 샤프트(10)가 수직하게 부설되고 타측면에 제1 샤프트(10)와 동일 축에 위치하여 수직하게 부설되는 제2 샤프트(14)가 구비된 판상의 플레이트(24); 일측 개구부에 의해 제1 샤프트(10)를 감싸면서 타측이 플레이트(24)의 제1 샤프트(10) 설치면에 고정되는 제1 벨로우즈(12); 일단에 개구가 형성되고 타단이 플레이트(24)의 제2 샤프트(14) 설치면에 부착되는 복수의 제2 벨로우즈(16); 및 제1 벨로우즈(12)의 일측 개구부와 연통하는 고압작용홀(32) 및 고압작용홀(32)과 동일면 상에 형성되어 제2 벨로우즈(16)의 개구와 연통하는 고압유로(38)가 마련되며, 플레이트(24)가 전후 이동가능하게 수납되는 하우징;을 포함한다.

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Номер записи: 71
11-05-2018 дата публикации

INTERIOR TEMPERATURE MAINTAINING DEVICE FOR PRESSURE VESSEL

Номер: KR101856464B1
Автор: JANG, HUN, MOK, YONG KYOON, KIM, YOON HO, CHOI, MIN YOUNG, KO, DAE GYUN, LEE, SUNG YONG, YOO, JONG SUNG
Принадлежит: KEPCO NUCLEAR FUEL CO., LTD.

The present invention relates to an interior temperature maintaining device for a pressure vessel, comprising: a pressure vessel provided with a main heater for heating a testing water to a testing temperature and maintaining the testing temperature; a preliminary heater for heating the testing water to the testing temperature before using the main heater; and a heat exchanger including an injection pipe for injecting the testing water of the preliminary heater into the pressure vessel and a discharge pipe for discharging the testing water of the pressure vessel while the injection pipe is inserted into the discharge pipe. COPYRIGHT KIPO 2018 ...

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Номер записи: 72
05-07-2018 дата публикации

충격흡수층을 구비하는 충격특성이 우수한 핵연료집합체용 지지격자

Номер: KR0101874379B1
Автор: 이재준, 박남규, 류주영, 천주홍, 유종성, 남채영
Принадлежит: 한전원자력연료 주식회사

... 본 발명은 핵연료집합체용 지지격자의 격자판 형상 및 각 격자판 사이의 결합구조에 관한 것으로서, 보다 구체적으로는, 충격흡수층을 구비하는 충격특성이 우수한 핵연료집합체용 지지격자에 관한 것이다. 본 발명의 일 실시예에 따른 충격흡수층을 구비하는 충격특성이 우수한 핵연료집합체용 지지격자는, 제1 방향으로 일정 간격 이격하여 상호 평행하게 배치되는 판형상의 복수의 제1 격자스트랩 및 복수의 제1 격자스트랩과 교차하도록 제1 방향과 직각인 제2 방향으로 일정 간격 이격하여 상호 평행하게 배치되는 판형상의 복수의 제2 격자스트랩을 구비하고, 제1 격자스트랩 및 제2 격자스트랩은 내부에 연료봉이 장입되는 복수의 단위격자셀을 형성하는 내부격자체; 내부격자체의 외곽을 둘러싸는 중간격자판; 및 중간격자판으로부터 일정 간극을 두고 중간격자판을 둘러싸도록 중간격자판의 둘레를 따라 배치되는 외부격자판;을 포함하고, 제1 격자스트랩 및 제2 격자스트랩 중앙부에는 일측을 향하여 돌출하는 스프링이 형성되고 스프링의 상부 및 하부 각각에는 타측으로 돌출하는 딤플이 형성될 수 있다.

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