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    • 25. 发明公开
    • 사용후핵연료용 크리프 시험장치
    • 用于燃油核燃料试验的装置
    • KR1020120118200A
    • 2012-10-26
    • KR1020110035634
    • 2011-04-18
    • 한국원자력연구원
    • 양용식국동학권형문장정남최종원
    • G21C17/06G21C23/00
    • G21C17/06G21C23/00Y02E30/40
    • PURPOSE: A creep test device for spent fuels is provided to constantly maintain a size of pressure provided to a specimen even though a creep test environment is suddenly changed. CONSTITUTION: A test unit(10) heats a specimen including spent fuels. The test unit provides a test environment of the specimen. A pressure unit(20) provides first pressure to the specimen. A control unit(30) constantly maintains a size of the first pressure of the pressure unit by connecting the test unit to a test environment change of the specimen. The control unit selectively changes the first pressure in the pressure unit into second pressure to maintain pressure.
    • 目的:提供一种用于乏燃料的蠕变试验装置,以便即使蠕变试验环境突然改变,也能始终保持提供给样品的压力大小。 构成:测试单元(10)加热包含乏燃料的试样。 测试单元提供样品的测试环境。 压力单元(20)向样品提供第一压力。 控制单元(30)通过将测试单元连接到样本的测试环境变化来始终保持压力单元的第一压力的大小。 控制单元选择性地将压力单元中的第一压力改变为第二压力以保持压力。
    • 27. 发明授权
    • 감쇄탱크
    • DECAY坦克
    • KR101166136B1
    • 2012-07-23
    • KR1020110045044
    • 2011-05-13
    • 한국원자력연구원
    • 서경우박용철서재광지대영윤주현
    • G21C23/00G21C19/307
    • G21C19/307G21C23/00Y02E30/40
    • PURPOSE: A decay tank is provided to increase delay time through an inner vertical baffle, an outer vertical baffle, and a distribution pipe connected to the inner vertical baffle. CONSTITUTION: A housing(102) has an internal space. An inner vertical baffle(104) is fixed to the inner upper side of the housing. An outer vertical baffle(106) accommodates the inner vertical baffle. A distribution pipe(120) is connected to the inside of the inner vertical baffle. A discharge pipe(134) is arranged through the bottom of the housing. A drain pipe(130) is installed at the bottom of the outer vertical baffle.
    • 目的:提供衰减槽,以通过内部垂直挡板,外部垂直挡板和连接到内部垂直挡板的分配管道来延长延迟时间。 构成:外壳(102)具有内部空间。 内部垂直挡板(104)固定到壳体的内侧上侧。 外部垂直挡板(106)容纳内部垂直挡板。 分配管(120)连接到内垂直挡板的内部。 排出管(134)穿过壳体的底部布置。 排水管(130)安装在外垂直挡板的底部。
    • 28. 发明公开
    • 핵연료 취급 기중기 시뮬레이터
    • 核燃料起重机模拟器
    • KR1020120034975A
    • 2012-04-13
    • KR1020100096399
    • 2010-10-04
    • 한전케이피에스 주식회사
    • 임영출김원경김철효이일성
    • G21C19/18G21C23/00G21D3/04
    • Y02E30/40G21C19/10G06F17/5009G21C19/18
    • PURPOSE: A nuclear fuel handling crane simulator is provided to reduce inspecting time and costs by accurately indicating the location and cause in which an error is created. CONSTITUTION: A controller(10) controls a nuclear fuel handling crane. The controller outputs an answer signal about control commands by receiving the control commands. An embedded board(20) outputs location information about a transfer command among the control commands. A computer(30) inputs various set values in the embedded board. A computer(40) for HMI(Human Machine Interface) determines whether an error is generated or not by checking the control commands of the controller and the answer signal of the embedded board. The computer for HMI indicates the generation of the error in screen. An error indication part(50) indicates blocks according to function. The error indication part indicates a generation signal route of the error by interpreting PLC data of the controller.
    • 目的:提供核燃料处理起重机模拟器,以通过准确地指示产生错误的位置和原因来减少检查时间和成本。 规定:控制器(10)控制核燃料处理起重机。 控制器通过接收控制命令输出关于控制命令的应答信号。 嵌入式板(20)在控制命令之间输出关于传送命令的位置信息。 计算机(30)在嵌入式板中输入各种设定值。 用于HMI(人机界面)的计算机(40)通过检查控制器的控制命令和嵌入式板的应答信号来确定是否产生错误。 HMI的计算机指示屏幕中出现错误。 错误指示部(50)根据功能指示块。 错误指示部分通过解释控制器的PLC数据来指示错误的生成信号路由。
    • 29. 发明公开
    • 핵연료 피복관 크러드 모사시험장치 및 방법
    • 核燃料管的模拟装置和方法
    • KR1020090092472A
    • 2009-09-01
    • KR1020080017728
    • 2008-02-27
    • 한국원자력연구원한국수력원자력 주식회사
    • 맹완영김우철김종환상쿤자오
    • G21C17/00G21C23/00
    • G21C17/001G21C3/06G21C17/017G21Y2002/103G21Y2004/20
    • A CRUD(Chalk River Unidentified Deposit) simulation apparatus of a nuclear fuel tube and a simulating method thereof are provided to preserve boron compounds inside the CRUD by rapidly cooling the CRUD. An inflow valve(20) is installed on an inflow tube(10) in order to control the inflow of the solution with high temperature and high pressure. A pressure tube(40) generates the CRUD by contacting the solution of the high temperature and high pressure with the nuclear fuel tube. An outflow valve(60) is installed on an outflow tube(50) in order to control the outflow of the solution with the high pressure and the high pressure. A branch tube(70) is branched from the inflow tube and the outflow tube. A branch value(80) is open to detour the solution with high temperature and high pressure through the inflow tube, the branch tube, and the outflow tube when the inflow valve and the outflow valve are closed. A pressure tube exhaust valve(90) prevents the re-dissolution of the water-soluble component of the CRUD.
    • 通过快速冷却CRUD,提供核燃料管的CRUD(Chalk River Unidentified Deposit)模拟装置及其模拟方法来保护CRUD内部的硼化合物。 流入阀(20)安装在流入管(10)上,以便控制溶液在高温高压下的流入。 压力管(40)通过使高温和高压的溶液与核燃料管接触来产生CRUD。 流出阀(60)安装在流出管(50)上,以便控制溶液在高压和高压下的流出。 分支管70从流入管和流出管分支。 当流入阀和流出阀关闭时,分支值(80)打开以通过流入管,分支管和流出管高温高压地迂回解决方案。 压力管排气阀(90)防止CRUD的水溶性成分的再溶解。
    • 30. 发明公开
    • 연구용원자로의 고속중성자 조사장치
    • 研究反应堆的快速中性辐射设备
    • KR1020090036336A
    • 2009-04-14
    • KR1020070101459
    • 2007-10-09
    • 한국원자력연구원
    • 김학성박상준전병진채희택박철김헌일
    • G21C23/00
    • A fast neutron irradiation facility of a research reactor is provided to maximize nuclear fuel by installing an irradiation hole at the outside of a core and reducing the interference with core reactivity. A fast neutron irradiation facility of a research reactor includes a reflector(430) which is on the outside of a reflector tank(432) while being submerged at a water tube. A core(410) is composed of the nuclear fuel bundle while being at the center of a nuclear reactor. The reflector is compose of heavy water or beryllium while surrounding the core, and an aluminum block(446) is closely adhered to the outer wall of the reflector while having a plurality of penetration holes. The nuclear fuel(442) is loaded into the aluminum block, and the nuclear fuel is inserted within a plurality of penetration holes. The high speed neutron radiation space block(448) is closely adhered to the other side of the aluminum block.
    • 提供研究堆的快速中子照射设备,通过在核心的外部安装照射孔并减少与核心反应性的干扰来最大化核燃料。 研究堆的快中子照射设备包括反射器(430),反射器(430)在反射器箱(432)的外侧被浸没在水管上。 核心(410)由核燃料束组成,同时处于核反应堆的中心。 反射器由围绕芯的重水或铍构成,并且铝块(446)紧密地粘附到反射器的外壁上,同时具有多个穿透孔。 核燃料(442)被装载到铝块中,并且核燃料被插入到多个穿透孔内。 高速中子辐射空间块(448)紧密地粘附在铝块的另一侧。