会员体验
专利管家(专利管理)
工作空间(专利管理)
风险监控(情报监控)
数据分析(专利分析)
侵权分析(诉讼无效)
联系我们
交流群
官方交流:
QQ群: 891211   
微信请扫码    >>>
现在联系顾问~
热词
    • 1. 发明公开
    • 원자로보호용기와 압축탱크를 이용한 비상노심냉각 방법과장치
    • 使用反应器保护容器和压缩罐冷却应急芯的方法和装置
    • KR1020020037105A
    • 2002-05-18
    • KR1020000067089
    • 2000-11-13
    • 한국원자력연구원한국전력공사
    • 김영인이두정윤주현배윤영조봉현김환열박천태최병선서재광강형석이준강한옥유승엽황영동이태호장문희
    • G21C15/18
    • Y02E30/40
    • PURPOSE: A method and apparatus is provided to cool the emergency core by using an iron protection container, compression tank with a cooling water and a natural circulation phenomenon in the reactor container, while achieving improved safety of integrated type nuclear reactor and reducing the amount of cooling water. CONSTITUTION: A nuclear reactor protection container(2) is installed around a nuclear reactor vessel(1), and a vapor generator(3) disposed within the nuclear reactor vessel is arranged to be connected to an external passive residual heat removal system(4). A compression tank(5) is arranged at the top of the nuclear reactor vessel in such a manner that a cooling water is injected into the compression tank. A method is characterized in that a small protection container with a high pressure is installed outside the nuclear reactor vessel, the cooling member emitted from the nuclear reactor vessel is cut off by using the increase pressure caused due to the flashing of the cooling member emitted during the accident of cooling member loss, and the emergency core cooling water is supplied in a passive manner by using the compression tank. The decay heat generated from the core is removed by the passive residual heat removing system using a natural circulation and stream generator disposed in the nuclear reactor vessel.
    • 目的:提供一种方法和装置,通过在反应堆容器中使用铁保护容器,具有冷却水的压缩罐和自然循环现象来冷却应急核心,同时实现综合型核反应堆的安全性的提高和减少 冷却水。 构成:核反应堆保护容器(2)安装在核反应堆容器(1)周围,并且设置在核反应堆容器内的蒸汽发生器(3)被设置成连接到外部被动余热除去系统(4) 。 压缩箱(5)以这样的方式设置在核反应堆容器的顶部,即将冷却水注入到压缩罐中。 一种方法的特征在于,将具有高压的小型保护容器安装在核反应堆外部,从核反应堆容器发射的冷却构件通过使用由于发射的冷却构件的闪烁而引起的增加压力被切断 冷却部件损失的事故,以及通过使用压缩罐而以被动方式供给应急芯冷却水。 通过使用设置在核反应堆容器中的自然循环和流发生器的被动余热除去系统来除去由芯产生的衰变热。
    • 3. 发明授权
    • 원자로보호용기와 압축탱크를 이용한 비상노심냉각 방법과장치
    • 用户名和密码
    • KR100419194B1
    • 2004-02-19
    • KR1020000067089
    • 2000-11-13
    • 한국원자력연구원한국전력공사
    • 김영인이두정윤주현배윤영조봉현김환열박천태최병선서재광강형석이준강한옥유승엽황영동이태호장문희
    • G21C15/18
    • Y02E30/40
    • PURPOSE: A method and apparatus is provided to cool the emergency core by using an iron protection container, compression tank with a cooling water and a natural circulation phenomenon in the reactor container, while achieving improved safety of integrated type nuclear reactor and reducing the amount of cooling water. CONSTITUTION: A nuclear reactor protection container(2) is installed around a nuclear reactor vessel(1), and a vapor generator(3) disposed within the nuclear reactor vessel is arranged to be connected to an external passive residual heat removal system(4). A compression tank(5) is arranged at the top of the nuclear reactor vessel in such a manner that a cooling water is injected into the compression tank. A method is characterized in that a small protection container with a high pressure is installed outside the nuclear reactor vessel, the cooling member emitted from the nuclear reactor vessel is cut off by using the increase pressure caused due to the flashing of the cooling member emitted during the accident of cooling member loss, and the emergency core cooling water is supplied in a passive manner by using the compression tank. The decay heat generated from the core is removed by the passive residual heat removing system using a natural circulation and stream generator disposed in the nuclear reactor vessel.
    • 目的:提供一种方法和设备,通过在反应器容器中使用铁保护容器,具有冷却水的压缩罐和自然循环现象来冷却应急核心,同时提高集成型核反应堆的安全性并减少 冷却水。 构成:核反应堆保护容器(2)围绕核反应堆容器(1)安装,并且布置在核反应堆容器内的蒸气发生器(3)被布置为连接到外部无源余热去除系统(4) 。 压缩罐(5)以这样的方式布置在核反应堆容器的顶部,使得冷却水被注入到压缩罐中。 一种方法,其特征在于,在核反应堆容器的外部安装高压的小保护容器,通过使用由于在期间发射的冷却构件的闪光所引起的增加的压力来切断从核反应堆容器排出的冷却构件 冷却部件损失事故以及应急核心冷却水通过使用压缩罐以被动方式供应。 由核心产生的衰变热通过使用布置在核反应堆容器中的自然循环和流发生器的被动余热去除系统去除。
    • 5. 发明授权
    • 단순 가ㆍ감압 싸이클을 이용한 자기가압기의 감압장치 및방법
    • 단순가ㆍ감압싸이클을이용한자기가압기의감압장치및방단순
    • KR100383817B1
    • 2003-05-14
    • KR1020000080231
    • 2000-12-22
    • 한국원자력연구원한국전력공사
    • 조봉현이두정윤주현배윤영김환열박천태최병선서재광강형석이준강한옥유승엽김영인황영동이태호장문희
    • G21C1/09
    • Y02E30/40
    • PURPOSE: A decompression device of self-pressurizer using simple pressure cycle and a method of the same are provided to reduce a pressure of a pressurizer to an air pressure by collecting a nitrogen gas in a gas cylinder. CONSTITUTION: A first process opens a magnetic pressurizer isolation valve(11) and a gas cylinder connection tube isolation tube(22), and exhausts a nitrogen gas from a magnetic pressurizer(10) into a gas supplementation tank(30). A second process opens a gas cylinder isolation valve(21) and makes a secondary equilibrium with a pressure of a gas cylinder(20). A third process exhausts the nitrogen gas from the gas supplementation tank(30) and collects the nitrogen gas in the gas cylinder(20). A fourth process opens a gas supplementation tank exhaustion tube isolation valve(32) and exhausts a water from the gas supplementation tank(30) into an exhaustion tank(50).
    • 目的:提供一种使用简单压力循环的自增压器的减压装置及其方法,以通过收集气瓶中的氮气将增压器的压力降低至气压。 结构:第一过程打开磁性稳压器隔离阀(11)和气瓶连接管隔离管(22),并将氮气从磁性稳压器(10)排出到气体补充罐(30)中。 第二过程打开气瓶隔离阀(21)并且利用气瓶(20)的压力进行二次平衡。 第三过程排出来自气体补充罐(30)的氮气并收集气瓶(20)中的氮气。 第四过程打开气体补充箱排气管隔离阀(32)并将来自气体补充箱(30)的水排出到排气箱(50)中。
    • 7. 发明授权
    • 소듐을 포함한 액체금속용 게이트 밸브장치
    • 用于具有钠的液体金属的门阀装置
    • KR101035994B1
    • 2011-05-23
    • KR1020090076177
    • 2009-08-18
    • 한국원자력연구원한국수력원자력 주식회사
    • 김태준김영일김성오이용범이태호박수기어재혁김종만정지영
    • G21C15/247
    • Y02E30/35
    • 소듐을 포함한 액체금속의 경화로 인한 오작동을 방지할 수 있는 소듐을 포함한 액체금속용 게이트 밸브장치가 개시된다. 개시된 본 발명에 의한 소듐을 포함한 액체금속용 게이트 밸브장치는, 고온의 소듐(Na)이 포함된 알칼리 금속(Li, K 등), 소듐-포타슘(Na-K) 합금, 납-비스무스(Pb-Bi) 합금 및 납(Pb)을 포함하는 액체금속을 취급하는 시설로 소듐을 포함한 액체금속을 공급하는 것으로서, 액체금속의 경로가 형성되는 밸브 몸체, 밸브 몸체 내에 설치되어 액체금속의 경로를 선택적으로 개폐시키는 게이트 및, 게이트를 액체금속의 경로를 개폐시키는 방향으로 가동시키는 스템을 포함하는 밸브유닛, 그리고, 게이트에 의해 개폐되는 액체금속의 경로를 가열하는 제1히터, 스템 측으로 유출되는 액체금속의 유출 경로를 가열하는 제2히터 및, 제1 및 제2히터의 온도를 측정 및 제어하는 온도제어부를 포함하는 히터유닛을 포함한다. 이러한 밸브유닛과 히터유닛을 일체로 형성한 구성에 의하면, 액체금속의 경로뿐만 아니라 스템 측으로 유출되는 유출 경로까지도 가열함에 따라 액체금속의 경화로 인한 밸브 오작동을 방지할 수 있고 유지/보수성이 좋게 된다.
      액체금속, 소듐, 밸브, 게이트, 가열, 히터, 벨로우즈, 벨로즈.
    • 8. 发明公开
    • 소듐 냉각 고속로의 모의 노심 가열장치
    • 用于在钠冷却快速反应器系统中加热模拟核心的装置
    • KR1020100120529A
    • 2010-11-16
    • KR1020090039393
    • 2009-05-06
    • 한국원자력연구원한국수력원자력 주식회사
    • 김태준한도희김성오이용범이태호어재혁박수기차재은한지웅
    • F27D11/10F27B3/20G21C17/00
    • F27D11/04F27B17/02F27D9/00F27D99/0006F27D2019/0037G21C17/00
    • PURPOSE: A device for heating a simulated core in a sodium cooled fast reactor system is provided to directly heat molten metal having a low melting point using an electrode rod provided with low-voltage and high-current power. CONSTITUTION: A device for heating a simulated core in a sodium cooled fast reactor system uses molten metal including alkali metal containing high-temperature sodium, sodium-potassium alloy, lead-bismuth alloy, and lead. The simulated core heating device includes an electrode rod(100) which is installed in the molten metal and heats the molten metal with low-voltage and high-current power. Single phase AC power is applied to the electrode rod through an electric wire which is connected only to the electrode plate of the electrode rod. The exterior of the electrode rod is coated with an insulator which is protected with a protective layer not to contact the molten metal.
    • 目的:提供一种用于加热钠冷快堆反应器系统中的模拟芯的装置,使用提供低电压和大电流功率的电极棒直接加热具有低熔点的熔融金属。 构成:用于加热钠冷快速反应器系统中的模拟芯的装置使用包括含有高温钠,钠 - 钾合金,铅 - 铋合金和铅的碱金属的熔融金属。 模拟的核心加热装置包括安装在熔融金属中的电极棒(100),并以低电压和高电流功率加热熔融金属。 通过仅连接到电极棒的电极板的电线将单相AC电力施加到电极棒。 电极棒的外部涂有绝缘体,绝缘体被保护层保护而不与熔融金属接触。
    • 9. 发明公开
    • 소듐냉각 고속로의 잔열제거용 중간 소듐루프에서의 소듐고화가능성을 배제한 피동 안전등급 잔열제거 시스템
    • 在中间加热去除钠循环中经过冷冻处理的被动安全等级退火除热系统
    • KR1020090066663A
    • 2009-06-24
    • KR1020070134316
    • 2007-12-20
    • 한국원자력연구원한국수력원자력 주식회사
    • 어재혁이태호박창규김성오
    • G21C15/18
    • Y02E30/34Y02E30/35
    • A passive safety-grade decay heat removal system from a sodium freezing issue at an intermediate heat removal sodium loop is provided to enhance operational reliability by connecting a heating air outlet of high temperature and an air channel of a sodium-air heat exchanger with each other. A passive safety-grade decay heat removal system from a sodium freezing issue at an intermediate heat removal sodium loop includes an outer air channel, a hot air outlet, and an air entrance nozzle(45). The outer air channel is formed from an outside to an inside of a nuclear reactor structure in order to receive external air from an outer air entrance. The hot air outlet is used for changing the direction of the received external air at a lower end of the nuclear reactor in order to cool an outer circumference of a reactor chamber and to induce the heated air to the outside of the nuclear reactor structure. The air entrance nozzle is used for inducing the heated air to an inside of a sodium-air heat exchanger.
    • 提供了一种在中间散热钠环路处由钠冷冻问题引起的被动安全等级的衰变散热系统,通过将高温加热空气出口与钠空气热交换器的空气通道相互连接来提高操作的可靠性 。 在中间除热钠环路处的钠冷冻问题的被动安全级衰变除热系统包括外部空气通道,热空气出口和空气入口喷嘴(45)。 外部空气通道从核反应堆结构的外部到内部形成,以便从外部空气入口接收外部空气。 热空气出口用于改变核反应堆下端接收到的外部空气的方向,以冷却反应室的外周,并将加热的空气引导到核反应堆结构的外部。 空气入口喷嘴用于将加热的空气引导到钠 - 空气热交换器的内部。