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    • 1. 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。
    • 3. 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。
    • 4. 发明公开
    • 수중 압력파에 견딜수 있는 복수기 열전달 튜브
    • 在水压波下耐热冷凝器的传热管
    • KR1020000020547A
    • 2000-04-15
    • KR1019980039204
    • 1998-09-22
    • 한국원자력연구원한국전력공사
    • 김주평이두정김종인김지호윤주현이준조봉현김환열김용완박천태최병선서재광강형석장문희김시환
    • F28D1/047
    • F28D1/0477F28D7/163
    • PURPOSE: A spiral heat transfer tube is provided to efficiently cope with the underwater pressure wave can be generated by the underwater explosion without using a vertical tube type heat delivery tube of a condenser used in a power plant. CONSTITUTION: A spiral heat exchange tube(3) has the both ends to be welded by a seawater separating plate(2). The seawater used for cooling water is flowed into a cooling water inlet(7) via a pipe(5) for the inflow of cooling water and then into the spiral heat exchange tube welded on the seawater separating plate. The seawater heated while condensing the vapors by flowing in the spiral heat exchange tube is discharged to a cooling water outlet(8) via the outlet of the spiral heat exchange tube and finally out of a condenser via a tube(6) for cooling water discharge. The heat transfer area per each tube is increased by multiple times compared to a vertical tube or a U-type tube so that the numbers of the heat exchange tubes can be reduced.
    • 目的:提供螺旋传热管,以有效应对水下爆炸产生的水下压力波,无需使用发电厂使用的冷凝器的垂直管式输送管。 构成:螺旋换热管(3)的两端用海水分离板(2)焊接。 用于冷却水的海水通过管道(5)流入冷却水入口(7),用于冷却水的流入,然后进入焊接在海水分离板上的螺旋换热管。 通过在螺旋形热交换管中流动而使蒸气冷凝的同时加热的海水经由螺旋形热交换管的出口排出到冷却水出口(8),最后通过管(6)排出冷凝器,以冷却排水 。 与垂直管或U型管相比,每个管的传热面积增加了多次,从而可以减少热交换管的数量。
    • 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. 发明公开
    • 안전주입탱크를 이용한 피동안전주입계통
    • 使用安全注射罐的被动安全注射系统
    • KR1020140010514A
    • 2014-01-27
    • KR1020120076241
    • 2012-07-12
    • 한국원자력연구원
    • 김영인문주형신수재이준김긍구이원재최순김태완김학노박천태유승엽배영민
    • G21C19/02
    • G21C15/18G21C1/32Y02E30/40
    • The present invention relates to a passive safety injection system using a safety injection tank, comprising a nuclear reactor containment building; a nuclear reactor installed in the nuclear reactor containment building; a safety injection tank which is filled with water and nitrogen gas; a safety injection pipe in which one end is connected to the side surface of the nuclear reactor while the other end is connected to the lower part of the safety injection tank to guide, to the inside of the nuclear reactor, water stored in the safety injection tank when the water level is reduced in the nuclear reactor due to a cooling material loss accident; a back pressure pipe in which one end is connected to the upper part of the nuclear reactor while the other end is connected to the upper part of the safety injection tank to guide, to the inside of the safety injection tank, the steam of the high temperature generated in the nuclear reactor when the cooling material loss accident is generated, wherein an orifice and a check valve are installed in a duct of the safety injection pipe, and a separation valve and a orifice are installed in a duct of the back pressure pipe, thereby introducing the water stored in the safety injection tank for hours into the inside of the nuclear reactor.
    • 本发明涉及一种使用安全注射罐的被动安全注射系统,包括核反应堆安全壳; 安装在核反应堆遏制建筑中的核反应堆; 一个充满水和氮气的安全注射罐; 安全注射管,其一端连接到核反应堆的侧表面,而另一端连接到安全注射罐的下部,以将存储在安全注射器中的水引导到核反应堆的内部 由于冷却材料损失事故造成核反应堆内的水位下降; 背压管,其一端连接到核反应堆的上部,而另一端连接到安全注射罐的上部,以将安全注射罐的蒸汽引导到安全注射罐的内部, 当产生冷却材料损失事故时在核反应堆中产生的温度,其中孔和止回阀安装在安全注射管的管道中,并且分离阀和孔口安装在背压管道的管道中 从而将储存在安全注射罐中的水引入核反应堆内部几小时。
    • 10. 发明授权
    • 피동살수계통을 이용한 일체형원자로 안전설비
    • 使用无源喷雾系统的整体反应器的安全特性
    • KR100856501B1
    • 2008-09-04
    • KR1020070034360
    • 2007-04-06
    • 한국원자력연구원한국수력원자력 주식회사
    • 김영인박천태강한옥이준이규형배규환김희철윤주현정영종김긍구박근배지성균
    • G21C15/18G21C15/00
    • Y02E30/40
    • A safe device for an integral reactor using a passive spray system is provided to lower a pressure and to reduce a manufacturing cost by reducing an internal pressure of a safe device vessel. A safe device for an integral reactor using a passive spray system includes a passive spray system(50), a collecting tank(60), a safe protection vessel(20), and a passive heat removing system(30). The passive spray system is installed on a higher position than a reactor collecting vessel, and sprays a cooling water by the gravitation when a cooling agent is lost. The collecting tank is installed on a circumference of the reactor collecting vessel, and is coupled to the reactor collecting vessel through a connection pipe. The safe protection vessel has the reactor collecting vessel, the passive spray system and the collecting tank. The passive heat removing system enables a steam emitted from a steam generator along a steam pipe to pass a condensed heat exchanger which is installed in a nuclear fuel re-supply tank installed outside the safe protection vessel. The passive heat removing system enables the steam to flow to the steam generator along a main water supply pipe.
    • 提供了一种使用被动喷雾系统的整体式反应器的安全装置,以通过降低安全装置容器的内部压力来降低压力并降低制造成本。 用于使用被动喷雾系统的整体反应堆的安全装置包括被动喷射系统(50),收集罐(60),安全保护容器(20)和被动除热系统(30)。 被动喷雾系统安装在比反应堆收集容器更高的位置,当冷却剂丢失时,通过重力喷射冷却水。 收集罐安装在反应堆收集容器的圆周上,并通过连接管联接到反应堆收集容器。 安全保护容器具有反应器收集容器,被动喷雾系统和收集罐。 被动除热系统使得从蒸汽发生器沿蒸汽管排出的蒸汽能够通过安装在安全保护容器外部的核燃料再供应罐中的冷凝热交换器。 被动除热系统使得蒸汽能够沿着主供水管流到蒸汽发生器。