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1. 发明公开

KR1020140087198A 캐스크 바스켓 지지체 审中-实审
标题翻译： CASK篮子支持
公开(公告)号：KR1020140087198A
公开(公告)日：2014-07-09
申请号：KR1020120156145
申请日：2012-12-28
申请人： 재단법인 포항산업과학연구원
发明人： 박신화 , 주성민
IPC分类号： G21F5/14
CPC分类号： G21F5/14 , G21Y2002/30 , G21Y2004/30
摘要： The present invention provides a lightweight cask basket support having excellent heat transfer properties as a cask basket support for supporting a plurality of cask baskets accommodating a fuel rod assembly. The cask basket support includes a support plate having a plurality of basket mounting units on which each cask basket is disposed; and a support rod which connects the support plate. The support plate is formed as a plurality of hollow structure beams is connected.
摘要翻译：本发明提供了一种具有优良传热性能的轻型桶装篮支架，作为用于支撑容纳燃料棒组件的多个木桶篮的木桶篮支架。木桶篮支撑件包括一个支撑板，该支撑板具有多个篮子安装单元，每个篮子篮被放置在该篮子上; 以及连接支撑板的支撑杆。支撑板形成为连接多个中空结构梁。

2. 发明公开

KR1020130035534A 파형강판을 이용한 원전격납구조물 有权
标题翻译：使用波形钢板的核反应堆混凝土容器
公开(公告)号：KR1020130035534A
公开(公告)日：2013-04-09
申请号：KR1020110099884
申请日：2011-09-30
申请人： 연세대학교 산학협력단
发明人： 김상효 , 최문석
IPC分类号： G21C13/02 , G21F7/00
CPC分类号： Y02E30/40 , G21C13/093 , G21Y2002/30 , G21Y2004/10
摘要： PURPOSE: A nuclear containment structure using a corrugated steel plate is provided to reduce a building cost and the weight of the structure and to enhance space occupancy by increasing a second section moment by using a liner member of a corrugated shape formed by bending a flat member. CONSTITUTION: A liner member(10) is formed into a corrugated shape having repeatedly arranged furrows and floors. A horizontal reinforcing member(20) increases combination force between the liner member and a concrete wall and is horizontally connected along an outer surface of the liner member. A first support unit is connected with the floors of the liner member and a combination unit is connected with the bottom of the first support unit. A second support unit is connected with an end of the combination unit and protruding in an upper direction.
摘要翻译：目的：提供使用波纹钢板的核容纳结构，以减少建筑成本和结构的重量，并且通过使用通过弯曲平坦构件形成的波纹形状的衬垫构件来增加第二截面力矩来增加空间占用。构成：衬套构件（10）形成为具有反复布置的沟槽和地板的波纹形状。水平加强构件（20）增加了衬套构件和混凝土壁之间的组合力，并且沿衬套构件的外表面水平连接。第一支撑单元与衬套构件的地板连接，组合单元与第一支撑单元的底部连接。第二支撑单元与组合单元的一端连接并沿上方突出。

3. 发明授权

KR101129463B1 The test facility for the cooling performance of the cedm coil 无效
标题翻译：公路卷材冷却性能的试验设备
公开(公告)号：KR101129463B1
公开(公告)日：2012-03-29
申请号：KR20100135542
申请日：2010-12-27
申请人： WOOJIN INC
发明人： LEE JAE HYUN , LEE SONG RYEOL
IPC分类号： G21C17/02 , G21C17/10
CPC分类号： G21C17/10 , G21Y2002/30 , G21Y2004/30 , Y02E30/40
摘要： PURPOSE: A control rod driving coil cooling performance test apparatus is provided to improve test accuracy by precisely arranging an environmental condition of a coil by adding a heater and a temperature controller. CONSTITUTION: An air heater(11) is installed on a fluid path entrance side of the upper part of a main body(10). A motor housing(12) is installed within a cooling shroud of the central part of the main body. Four motor housing heaters(13) are installed in side of the motor housing. The motor housing heater maintains surface temperature of the motor housing by being connected to a temperature controller of an electric panel(15) and a thermocouple(16). A blower(23) is installed on a flow path exit side of a pipe structure(20).
摘要翻译：目的：提供一种控制棒驱动线圈冷却性能测试装置，通过添加加热器和温度控制器精确地布置线圈的环境条件来提高测试精度。构成：空气加热器（11）安装在主体（10）的上部的流体入口侧。电动机壳体（12）安装在主体的中心部分的冷却护罩内。四个电机外壳加热器（13）安装在电机外壳的侧面。马达壳体加热器通过连接到电气面板（15）和热电偶（16）的温度控制器来维持马达壳体的表面温度。鼓风机（23）安装在管道结构（20）的流路出口侧。

4. 发明公开

KR1020030029653A 구획실의 외부와 내부 사이를 연결하기 위한 시스템 失效
标题翻译： 구획실의외부와내부사이를연결하기위한시스템
公开(公告)号：KR1020030029653A
公开(公告)日：2003-04-14
申请号：KR1020037002304
申请日：2001-08-13
申请人： 아스펙틱 테크놀러지스 소시에테 어나니머스
发明人： 틸리,쟈크 , 반데카세리에,크리스티안
IPC分类号： G21F7/005
CPC分类号： G21F7/005 , G21F7/047 , G21Y2002/206 , G21Y2002/30 , G21Y2004/30 , Y10T292/03 , Y10T292/202 , Y10T292/225 , Y10T403/595
摘要： 구획실의 내부와 외부 사이를 연결하는 시스템으로서, 구획실 벽을 통과하는 도어 개구, 벽과 결합될 수 있는 커넥터 바디를 포함하며, 그리고 구획실을 관통하는 연결 포트와 커넥터 바디상의 제거가능한 커버를 가진다. 바디는 도어 개구와 결합되고 그리고 구획실내에 내부 도어가 결합되고 커버를 제거한다. 바람직한 구성은 단일 신뢰 밀봉부 라인을 형성한다. 시스템은 특히 살균 구획실에 특히 적절하다.
摘要翻译：一种用于在隔间的内部和外部之间建立连接的系统，该系统包括穿过隔间壁的门开口，可与壁接合并具有穿过其的连接端口的连接器主体以及位于连接器主体上的可移除盖。车身与车门开口接合，车厢内的内门接合并移除车门盖。一个优选的结构创建了一个单一的置信密封线。该系统特别适用于无菌室。

5. 发明授权

KR1019940004770B1 데브리 트랩을 갖는 핵 연료 집합체 失效
标题翻译：核燃料包括废弃物
公开(公告)号：KR1019940004770B1
公开(公告)日：1994-05-28
申请号：KR1019860006522
申请日：1986-08-07
申请人： 씨비에스 코퍼레이션
发明人： 해리맥스페라리 , 존프란시스윌슨
IPC分类号： G21C3/30
CPC分类号： G21C3/3206 , G21C3/34 , G21Y2002/101 , G21Y2002/30 , G21Y2004/30 , Y02E30/40
摘要： 내용없음.

6. 发明授权

KR1019900004868B1 가압수형 원자로의 상부 내부 장치 失效
标题翻译：压水反应堆上部内部装置
公开(公告)号：KR1019900004868B1
公开(公告)日：1990-07-08
申请号：KR1019820005424
申请日：1982-12-03
申请人： 프라마토메꽁빠뉘
发明人： 쟝폴밀롯-3
IPC分类号： G21C7/00
CPC分类号： G21C7/08 , G21Y2002/30 , G21Y2002/302 , G21Y2004/30 , G21Y2004/40 , Y02E30/32 , Y02E30/39
摘要： The reactor core contains fuel rod assemblies (a) producing thermal neutrons; and fuel rod assemblies (b) producing epithermal neutrons. The core is located below a top plate carrying an assembly of guide tubes for contol rods. Each tube contains a vertical row of horizontal, perforated plates and perofrated perforated sheaths forming guides for the control rods. Each plate and each sheath contains two holes guiding the control rods used in one type of assembly (a); and two more holes guiding the control rods used in the other type of assembly (b). The control rod guidance system can be used either in a conventional reactor. or in a sub-moderated reactor.
摘要翻译：反应堆堆芯包含燃料棒组件（a），产生热中子; 和燃料棒组件（b）生产超热中子。芯部位于承载用于轮廓杆的导向管组件的顶板下方。每个管包含一排垂直的多孔板和带孔的穿孔护套，用于形成用于控制棒的引导件。每个板和每个护套包含引导在一种类型的组件（a）中使用的控制棒的两个孔; 以及另外两个引导在另一种类型的组件（b）中使用的控制棒的孔。控制棒引导系统可以在常规反应器中使用。或在亚慢化反应器中。

7. 发明授权

KR101410771B1 이물질 유입 방지장치를 갖는 안내관 有权
标题翻译：导管与外部物品防护装置
公开(公告)号：KR101410771B1
公开(公告)日：2014-06-24
申请号：KR1020120152265
申请日：2012-12-24
申请人： 한국원자력연구원
发明人： 이종민 , 류정수 , 조영갑
IPC分类号： G21C13/00
CPC分类号： Y02E30/40 , G21C13/028 , G21C19/28 , G21Y2002/30 , G21Y2002/50 , G21Y2004/10
摘要： The present invention relates to a guide tube having a foreign substance insertion prevention apparatus capable of preventing foreign substances from flowing into a core if the opening of the core is required during an operation of a reactor such an investigation test. The guide tube comprises: two or more rotation brackets which are fixed to the end periphery surface of the guide tube to be rotatable; a cover segment which is integrally fixed to the rotation brackets, and opens and closes an aperture unit of the guide tube; a rotating arm which is fixed to the rotation brackets to be rotatable; and a connecting arm which is fixed to the top of the rotating arm to be rotatable, wherein the minimum distance of the connecting arm from the center axis of the guide tube is smaller than a radius of the guide tube.
摘要翻译：本发明涉及具有异物插入防止装置的引导管，其能够在反应器的操作期间如果需要开启核心时防止异物流入核心。引导管包括：两个或更多个旋转托架，其固定到引导管的端部周边表面以可旋转; 一个固定在旋转支架上的盖部分，并且打开和关闭导管的孔单元; 旋转臂，其被固定到所述旋转托架以可旋转; 以及连接臂，其被固定到所述旋转臂的顶部以能够旋转，其中所述连接臂与所述引导管的中心轴线的最小距离小于所述引导管的半径。

8. 发明公开

KR1020110045660A 열수력 안전해석코드를 이용한 원자로 노심 평가방법 有权
标题翻译：使用热液压安全分析代码的核反应堆核心评估方法
公开(公告)号：KR1020110045660A
公开(公告)日：2011-05-04
申请号：KR1020090102323
申请日：2009-10-27
申请人： 한국수력원자력 주식회사
发明人： 김요한 , 하상준 , 양창근 , 이동혁 , 최훈 , 김세윤
IPC分类号： G21C17/00
CPC分类号： G21C17/00 , G21D3/06 , G21Y2002/30 , G21Y2004/20
摘要： PURPOSE: A nuclear reactor core assessment method using a thermal hydraulic safety analysis code is provided to evaluate a reactor core through single code system by modeling a vapor supply system, the hot water pipe of the reactor core, and the high temperature point of the reactor core. CONSTITUTION: In a nuclear reactor core assessment method using a thermal hydraulic safety analysis code, a model of a vapor supply system model is generated(101). A model of the hot water pipe of the reactor core is generated(103). A model of the high temperature of the reactor core is generated(105). The temperature, pressure, and flow rate of the vapor supply system is calculated(107). The heat output and heat flux, or nucleate boiling ratio breakaway rate of the hot water pipe of the reactor core are calculated. The high temperature point distribution of the reactor core and average enthalpy in radial direction or the maximum temperature of a covering material are calculated(109) nucleate boiling ratio breakaway rate or average enthalpy in radial direction is analyzed(111) A model of the high temperature water pipe of the reactor core is generated.
摘要翻译：目的：提供使用热液压安全分析代码的核反应堆核心评估方法，通过对蒸汽供应系统，反应堆堆芯的热水管和反应堆的高温点进行建模，通过单码系统评估反应堆堆芯核心。构成：在使用热液压安全分析代码的核反应堆核心评估方法中，产生蒸汽供应系统模型的模型（101）。产生反应堆堆芯的热水管的模型（103）。产生反应堆堆芯的高温模型（105）。计算蒸气供应系统的温度，压力和流量（107）。计算反应堆核心的热水管的热输出和热通量或核沸腾比分离率。计算反应堆芯的高温点分布和半径方向的平均焓或覆盖材料的最高温度（109）分析核沸腾比分离率或径向平均焓（111）高温模型产生反应堆堆芯的水管。

9. 发明授权

KR101002008B1 Appratus for design basis accident test 无效
标题翻译：设计基准事故检测设计
公开(公告)号：KR101002008B1
公开(公告)日：2010-12-16
申请号：KR20100077742
申请日：2010-08-12
申请人： KOREA MACH & MATERIALS INST
发明人： SONG CHI SUNG , KIM JAE HYUNG , KIM BYUNG DUCK
IPC分类号： G21C17/00 , G21D3/04
CPC分类号： Y02E30/40 , G21C17/001 , G21D3/04 , G21Y2002/30 , G21Y2004/30
摘要： PURPOSE: An apparatus for testing a design basis accident is provided to efficiently control a fluid level in a test chamber by discharging the fluid in the test chamber according to the sensing information of a fluid level sensor. CONSTITUTION: A buffer tank(140) is connected to a test chamber(120) to have a fluid level corresponding to the fluid level of the test chamber. A mixing tank(160) stores fluid(50) discharged from the buffer tank. A fluid level controller(180) controls the fluid level in the test chamber and the buffer tank and includes a fluid level sensor, a discharge pump, and an automatic valve. The fluid level sensor senses the fluid level in the buffer tank. The discharge pump discharges the fluid from the buffer tank to the mixing tank according to the sensing information of the fluid level sensor. The automatic valve is opened and closed according to the sensing information of the fluid level sensor.
摘要翻译：目的：提供一种用于测试设计基准事故的设备，以根据液位传感器的感测信息，通过在测试室中排放流体来有效地控制测试室中的液位。构成：缓冲罐（140）连接到测试室（120）以具有与测试室的液面相对应的液面。混合罐（160）存储从缓冲罐排出的流体（50）。液位控制器（180）控制测试室和缓冲罐中的液位，并包括液位传感器，排放泵和自动阀。液位传感器感测缓冲罐中的液位。排放泵根据液位传感器的感测信息将液体从缓冲罐排放到混合罐。自动阀根据液位传感器的检测信息打开和关闭。

10. 发明公开

KR1020100125147A 원자로 용기 하부헤드 고열속 모사장치 失效
标题翻译：用于核反应堆船的较低热源的模拟器
公开(公告)号：KR1020100125147A
公开(公告)日：2010-11-30
申请号：KR1020090044204
申请日：2009-05-20
申请人： (주)필로소피아
发明人： 서균렬
IPC分类号： G21C17/00
CPC分类号： G21C17/001 , G21C15/12 , G21Y2002/30 , G21Y2004/30
摘要： PURPOSE: A simulator of a lower head of a nuclear reactor is provided to prevent welded parts from being damaged due to a high temperature by removing the welded part between a heating unit and the lower head. CONSTITUTION: A hemisphere heating unit(100) comprises a lower hemispheric shell and a melt simulator. The lower hemispheric shell simulates the lower head of a nuclear reactor container. The melt simulator has a plurality of heating bar insertion holes. The melt simulator simulates the core melt. A connection ring(200) is arranged on the upper edge of the hemispheric heating unit. A core cylinder simulator(300) has a hollow cylindrical shape and is arranged on the connection ring.
摘要翻译：目的：提供核反应堆下头模拟器，通过去除加热单元和下头之间的焊接部分，防止焊接部件由于高温而损坏。构成：半球加热单元（100）包括下半球壳和熔体模拟器。下半球壳模拟核反应堆容器的下部头部。熔体模拟器具有多个加热棒插入孔。熔体模拟器模拟核心熔体。连接环（200）布置在半球形加热单元的上边缘上。芯筒模拟器（300）具有中空圆柱形并布置在连接环上。

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