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1. 发明授权

KR100909443B1 안전밸브 성능시험장치 및 시험방법 有权
标题翻译：安全阀试验装置及方法
公开(公告)号：KR100909443B1
公开(公告)日：2009-07-30
申请号：KR1020080116753
申请日：2008-11-24
申请人： 한국수력원자력 주식회사
发明人： 오승종 , 정동욱 , 박종운 , 권갑주 , 김창현
IPC分类号： G01M13/00 , F16K17/00 , G01M99/00
CPC分类号： G01M13/005
摘要： A performance testing device of a safety valve and a testing method of the same are provided to perform an accurate test by conducing the test under the identical driving conditions with a compressor safety valve. A performance testing device of a safety valve comprises: a compressor(21) storing the steam vapor generated by an electric heating unit(22) at the high pressure; a specimen cup(41) receiving the steam vapor, whose the flow rate and the temperature of is controlled by the compressor and storing the vapor at the high pressure in order to provide the test pressure to a target safety valve(48); a pressure emission tank collecting the water by condensing the emitted vapor of a target safety valve(48) while storing the desalted water to be supplied to the compressor; and a water feeding pump supplying the water stored in the pressure emission tank to the compressor.
摘要翻译：提供一种安全阀的性能测试装置及其测试方法，以通过使用压缩机安全阀在相同的驾驶条件下进行试验来进行精确的测试。安全阀的性能测试装置包括：压缩机（21），存储由电加热单元（22）在高压下产生的蒸汽蒸汽; 接收蒸汽的样品杯（41），其流量和温度由压缩机控制并将蒸汽储存在高压下，以向目标安全阀（48）提供测试压力; 压力释放箱，通过在将要供给压缩机的脱盐水储存在一起的同时冷凝目标安全阀（48）的排出的蒸汽来收集水; 以及将储存在压力释放箱中的水供给压缩机的给水泵。

2. 发明公开

KR1020010060933A 노심용융물-콘크리이트 반응 저지를 위한 노심용융물노외유지 장치 无效
标题翻译：用于维持核心熔融材料外部烧结的装置用于停止核心熔融材料 - 混凝土反应
公开(公告)号：KR1020010060933A
公开(公告)日：2001-07-07
申请号：KR1019990063392
申请日：1999-12-28
申请人： 한국수력원자력 주식회사
发明人： 박종운 , 오승종 , 티이.지이.데오파노스
IPC分类号： G21C9/016
CPC分类号： G21C9/016 , G21Y2002/201 , G21Y2002/207 , G21Y2002/50 , G21Y2004/30 , Y02E30/40
摘要： PURPOSE: An apparatus for maintaining a core molten material outside a furnace is provided to stop the core molten material-concrete reaction so as to cope with very serious accidents due to continued loss of the cooling function for a nuclear reactor fuel. CONSTITUTION: In an apparatus for maintaining a core molten material outside a furnace for alleviating the core molten material-concrete reaction which is installed for relieving danger due to unpredictable accidents exceeding an accident considered based on the design standard of a nuclear power plant, the apparatus comprises a horizontal jacket pipe (110) consisting of the shell boundary surface of the bottom (200) of a nuclear reactor cavity, wherein cooling water inlet holes (111) having an appropriate density are formed at the lower half part of the horizontal jacket pipe (110) so that cooling water is flown in from the bottom; a vertical discharge pipe connected in a shape of the tail of a wild goose so that the vertical discharge pipe is reciprocally connected to both sides of the horizontal jacket pipe (110); and a cooling water supplying part installed at the lower part of the horizontal jacket pipe (110) so that cooling water is flown in from the total area of the bottom.
摘要翻译：目的：提供一种用于在炉外保持芯熔融材料的装置，以阻止芯熔融材料 - 混凝土反应，以应对由于核反应堆燃料的冷却功能的持续损失而引起的非常严重的事故。构成：在用于在炉外保持芯熔融材料以减轻核心熔融材料 - 混凝土反应的装置中，用于缓解因超过基于核电站设计标准考虑的事故的不可预知的事故而导致的危险，该装置包括由核反应堆空腔的底部（200）的壳边界面构成的水平套管（110），其中具有适当密度的冷却水入口孔（111）形成在水平套管的下半部（110），使得冷却水从底部流入; 垂直排放管，其连接有野鹅尾部的形状，使得垂直排出管与水平套管110的两侧往复连接; 以及安装在水平套管（110）的下部的冷却水供给部，使得冷却水从底部的总面积流入。

3. 发明授权

KR100436978B1 원자력발전소의 원자로 공동구조 失效
标题翻译： 원자력발전소의원자로공동구조
公开(公告)号：KR100436978B1
公开(公告)日：2004-06-23
申请号：KR1020010070904
申请日：2001-11-15
申请人： 한국수력원자력 주식회사
发明人： 임혁순 , 정대율 , 김성환 , 박종운 , 유호종 , 윤순철 , 황익규
IPC分类号： G21C9/00
CPC分类号： Y02E30/40
摘要： PURPOSE: A reactor cavity geometric structure of nuclear power plant is provided to prevent the discharge of radioactive material by integrating 90% of the fragments of melted material on a core debris chamber. CONSTITUTION: The first discharging slot(31) is provided with a reactor cavity in which fragments of a reactor vessel(20) and melted material discharged from the reactor vessel(20) are gathered to exchange heat. The second discharging slot(32) is provided with a core debris chamber(22) which interferes the fragments discharged from the first discharging slot(31) to collect them in the reactor cavity. The third discharging slot(31) is provided with an over-pressure emitting damper(23) which makes slow the discharging speed of the melted material from the second discharging slot(32). The second and third discharging slot(32,33) are provided on a wall(40) that accommodates the reactor vessel(20). The first discharging slot(31) is provided on a concrete base(30) which is located on a lower of the reactor vessel(20).
摘要翻译：目的：提供核电站的反应堆腔体几何结构，以通过将90％的熔融材料碎片集成在核心碎屑室上来防止放射性物质的排放。组成：第一排放槽（31）设有反应器腔，反应器容器（20）的碎片和从反应器容器（20）排出的熔化材料聚集在该反应器腔中以交换热量。第二排放槽（32）设置有核心碎屑室（22），其干扰从第一排放槽（31）排放的碎片以将它们收集在反应堆腔中。第三排出槽（31）设置有过压发射阻尼器（23），该过压发射阻尼器使熔化材料从第二排出槽（32）的排出速度减慢。第二和第三排放槽（32,33）设置在容纳反应器容器（20）的壁（40）上。第一卸料槽（31）设置在位于反应堆容器（20）下部的混凝土基座（30）上。

4. 发明公开

KR1020030040918A 원자로 비상 냉각장치 无效
标题翻译：原子反应堆紧急冷却装置
公开(公告)号：KR1020030040918A
公开(公告)日：2003-05-23
申请号：KR1020010071582
申请日：2001-11-17
申请人： 한국수력원자력 주식회사
发明人： 김성환 , 임혁순 , 정대욱 , 정대율 , 박종운 , 변성철 , 황익규 , 김인영
IPC分类号： G21C15/00
CPC分类号： Y02E30/40
摘要： PURPOSE: An emergency coolant apparatus of an atomic reactor is provided to prevent the damage of a reactor vessel by cooling core meltdown materials within the reactor vessel. CONSTITUTION: A water source(60) is filled with a cooling water. A supplying tube(80) connects the water source(60) to a reactor cavity(50) formed on a basic unit located on a lower end of a reactor vessel(10). A pump(70) is mounted on a path of the supplying tube(80). A valve is mounted on a path of the supplying tube(80) to control the flowing of the cooling water supplied from the water source(60). The supplying tube(80) has a control unit comprised of a sensing unit(90) for detecting over-heating state and a control unit(95) for controlling power to operate a work of the pump(70).
摘要翻译：目的：提供原子反应堆的应急冷却装置，以通过冷却反应堆容器内的核心熔化材料来防止反应堆容器的损坏。构成：水源（60）填充有冷却水。供应管（80）将水源（60）连接到形成在位于反应堆容器（10）的下端上的基本单元上的反应器空腔（50）。泵（70）安装在供给管（80）的路径上。阀安装在供给管（80）的路径上，以控制从水源（60）供应的冷却水的流动。供给管（80）具有由用于检测过热状态的感测单元（90）和用于控制用于操作泵（70）的工作的动力的控制单元（95）构成的控制单元。

5. 发明公开

KR1020010063656A 강화된 열차폐체를 활용한 원자로용기 외벽냉각 시스템 无效
标题翻译：使用加强型热屏蔽体的反应器容器冷却系统
公开(公告)号：KR1020010063656A
公开(公告)日：2001-07-09
申请号：KR1019990060843
申请日：1999-12-23
申请人： 한국수력원자력 주식회사
发明人： 박종운 , 이재성 , 오승종
IPC分类号： G21C15/24 , G21C15/18
CPC分类号： Y02E30/40
摘要： PURPOSE: A cooling system for a reactor container using a reinforced thermal shield body is provided to more rapidly supply cooling water toward a portion between the container and the reinforced thermal shield body if required without a separate air conditioning passage and with reduced number of valves. CONSTITUTION: A cooling water collecting unit can trap cooling water with minimizing the internal volume between the reactor container(300), and is reinforced by a thermal shield body(110) for resist the weight of the cooling water. A feeding unit(200) is branched from an existing cooling water feeding pipe(230) between a boric acid water supplement pump(220) and a nuclear fuel reload water tank(210). Double remote control valves(240,241) are closed under normal operation condition, and are opened to supply cooling water through the cooling water feeding pipe(230) if required.
摘要翻译：目的：提供一种用于使用加强型热屏蔽体的反应堆容器的冷却系统，以便在不需要单独的空气调节通道和减少阀门数量的情况下，更快地向容器和加强型热屏蔽体之间的部分提供冷却水。构成：冷却水收集单元可以使反应堆容器（300）内的内部容积最小化来收集冷却水，并且由热屏蔽体（110）加强以抵抗冷却水的重量。进料单元（200）从现有的冷却水供给管（230）在硼酸水补充泵（220）和核燃料重新加载水箱（210）之间分支。双重遥控阀（240,241）在正常操作状态下关闭，如果需要，打开以通过冷却水供给管（230）供应冷却水。

6. 发明公开

KR1020030040575A 원자력발전소의 원자로 공동구조 失效
标题翻译：核动力厂的反应堆密度几何结构
公开(公告)号：KR1020030040575A
公开(公告)日：2003-05-23
申请号：KR1020010070904
申请日：2001-11-15
申请人： 한국수력원자력 주식회사
发明人： 임혁순 , 정대율 , 김성환 , 박종운 , 유호종 , 윤순철 , 황익규
IPC分类号： G21C9/00
CPC分类号： Y02E30/40
摘要： PURPOSE: A reactor cavity geometric structure of nuclear power plant is provided to prevent the discharge of radioactive material by integrating 90% of the fragments of melted material on a core debris chamber. CONSTITUTION: The first discharging slot(31) is provided with a reactor cavity in which fragments of a reactor vessel(20) and melted material discharged from the reactor vessel(20) are gathered to exchange heat. The second discharging slot(32) is provided with a core debris chamber(22) which interferes the fragments discharged from the first discharging slot(31) to collect them in the reactor cavity. The third discharging slot(31) is provided with an over-pressure emitting damper(23) which makes slow the discharging speed of the melted material from the second discharging slot(32). The second and third discharging slot(32,33) are provided on a wall(40) that accommodates the reactor vessel(20). The first discharging slot(31) is provided on a concrete base(30) which is located on a lower of the reactor vessel(20).
摘要翻译：目的：提供核电站的反应堆腔体几何结构，以防止放射性物质通过将90％的熔融材料碎片整合在核心碎片室上而排放。构成：第一排放槽（31）设置有反应器空腔，反应器容器（20）的碎片和从反应器容器（20）排出的熔融材料被聚集以交换热量。第二排放槽32设置有芯屑室（22），其干扰从第一排放槽（31）排出的碎片，以将它们收集在反应器腔中。第三排放槽31设置有过压发射阻尼器23，其使来自第二排放槽32的熔融材料的排出速度变慢。第二和第三排放槽（32,33）设置在容纳反应堆容器（20）的壁（40）上。第一排放槽（31）设置在位于反应器容器（20）的下部的混凝土基座（30）上。

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