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1. 发明申请

WO2010013859A1 STEEL PLATE STRUCTURE 审中-公开
标题翻译：钢板结构
公开(公告)号：WO2010013859A1
公开(公告)日：2010-02-04
申请号：PCT/KR2008/004830
申请日：2008-08-20
申请人： KOREA HYDRO & NUCLEAR POWER CO., LTD , KOREA POWER ENGINEERING COMPANY, INC. , LEE, Han-Woo , KIM, Jong-Hak , SUN, Won-Sang , HWANG, Geun-Ha , LEE, Kwang-Jae , PARK, Dong-Su
发明人： LEE, Han-Woo , KIM, Jong-Hak , SUN, Won-Sang , HWANG, Geun-Ha , LEE, Kwang-Jae , PARK, Dong-Su
IPC分类号： E04C5/03
CPC分类号： E04C5/03
摘要： Disclosed is a steel plate structure that includes: a first surface plate and a second surface plate, which are separated from each other and each of which has one side facing each other; a strut, which maintains the separation distance between the first surface plate and the second surface plate; an H-shaped member, which is attached along a horizontal direction to one side of the first surface plate such that a flange of the H-shaped member faces one side of the first surface plate; and a mechanical anchoring device, which is attached to the other side of the first surface plate in correspondence with the H-shaped member and to which a steel bar is coupled. Since no holes, through which to the steel bars pass, are formed into the surface plate when attaching a beam or slab to a steel plate concrete wall, there are no losses in cross-sectional area, and structural integrity can be improved.
摘要翻译：公开了一种钢板结构，其包括：第一表面板和第二表面板，它们彼此分离并且每个具有面对的一个侧面; 支柱，其保持第一表面板和第二表面板之间的间隔距离; H形构件，其沿着水平方向附接到所述第一表面板的一侧，使得所述H形构件的凸缘面向所述第一表面板的一侧; 以及机械锚定装置，其与H形构件相对应地连接到第一表面板的另一侧并且钢筋连接到该锚固装置。由于在钢板混凝土壁上安装梁或板坯时，钢筋通过的孔不会形成在表面板中，所以横截面积没有损失，可以提高结构完整性。

2. 发明申请

WO2010013858A1 STEEL PLATE STRUCTURE AND STEEL PLATE CONCRETE WALL 审中-公开
标题翻译：钢板结构和钢板混凝土墙
公开(公告)号：WO2010013858A1
公开(公告)日：2010-02-04
申请号：PCT/KR2008/004829
申请日：2008-08-20
申请人： KOREA HYDRO & NUCLEAR POWER CO., LTD , KOREA POWER ENGINEERING COMPANY, INC. , LEE, Han-Woo , KIM, Jong-Hak , SUN, Won-Sang , HWANG, Geun-Ha , LEE, Kwang-Jae , PARK, Dong-Su
发明人： LEE, Han-Woo , KIM, Jong-Hak , SUN, Won-Sang , HWANG, Geun-Ha , LEE, Kwang-Jae , PARK, Dong-Su
IPC分类号： E04B2/86
CPC分类号： E04B2/8635
摘要： A steel plate structure and a steel plate concrete wall are disclosed. The steel plate structure may include: a pair of steel plates that are separated from each other with one side of one steel plate facing one side of the other steel plate such that a space is defined in-between; a strut maintaining a distance between the pair of steel plates; and a perforated pipe positioned in the space that extends from one end of the space to the other end of the space and has a multiple number of holes formed therein. The steel plate structure can effectively displace vapor created in the steel plate concrete wall by high levels of heat, to prevent the steel plate concrete wall from expanding or bursting and to improve durability.
摘要翻译：公开了一种钢板结构和钢板混凝土墙。钢板结构可以包括：一对钢板，其彼此分离，一个钢板的一侧面对另一个钢板的一侧，使得在其间限定空间; 保持一对钢板之间的距离的支柱; 以及穿孔管，其定位在从所述空间的一端延伸到所述空间的另一端的空间中，并且具有形成在其中的多个孔。钢板结构可以通过高水平的热量有效地排除钢板混凝土墙体产生的蒸汽，防止钢板混凝土墙体膨胀或爆裂，提高耐久性。

3. 发明申请

WO2010013857A1 STEEL PLATE STRUCTURE AND STEEL PLATE CONCRETE WALL 审中-公开
标题翻译：钢板结构和钢板混凝土墙
公开(公告)号：WO2010013857A1
公开(公告)日：2010-02-04
申请号：PCT/KR2008/004828
申请日：2008-08-20
申请人： KOREA HYDRO & NUCLEAR POWER CO., LTD , KOREA POWER ENGINEERING COMPANY, INC. , LEE, Han-Woo , NOH, Sang-Hoon , SUN, Won-Sang , HWANG, Geun-Ha , LEE, Kwang-Jae , PARK, Dong-Su
发明人： LEE, Han-Woo , NOH, Sang-Hoon , SUN, Won-Sang , HWANG, Geun-Ha , LEE, Kwang-Jae , PARK, Dong-Su
IPC分类号： E04B2/86
CPC分类号： E04B2/8635 , E04B2/8605
摘要： A steel plate structure for forming a wall by casting concrete therein includes a pair of steel plates, which are separated from each other and in which one surface of one of the pair of steel plates faces one surface of the other of the pair of steel plates, a first structural member, which is rigidly joined along a direction of gravity to one surface of the steel plates such that one end of the first structural member is protruded outward from one end of the steel plates and the other end of the first structural member is receded inward from the other end of the steel plates, and a strut, which maintains a separation distance between the pair of steel plates. Thus, the overall thickness of the steel plate concrete wall can be reduced so as to allow better welding properties and increase in the unit module size.
摘要翻译：用于通过铸造混凝土形成壁的钢板结构包括一对钢板，它们彼此分离，并且一对钢板中的一个的一个表面面对一对钢板的另一个的一个表面，所述第一结构构件沿着重力方向刚性地连接到所述钢板的一个表面，使得所述第一结构构件的一端从所述钢板的一端向外突出，并且所述第一结构构件的另一端从钢板的另一端向内退出，并且保持一对钢板之间的间隔距离的支柱。因此，可以减小钢板混凝土墙的整体厚度，以便允许更好的焊接性能和单元模块尺寸的增加。

4. 发明申请

WO2008048031A1 LIQUID-METAL-COOLED FAST REACTOR CORE COMPRISING NUCLEAR FUEL ASSEMBLY WITH NUCLEAR FUEL RODS WITH VARYING FUEL CLADDING THICKNESS IN EACH OF THE REACTOR CORE REGIONS 审中-公开
标题翻译：液体 - 金属冷却快速反应器核心，包含核燃料组件的核燃料组件，每个反应堆核心区域具有变化的燃料密封层厚度
公开(公告)号：WO2008048031A1
公开(公告)日：2008-04-24
申请号：PCT/KR2007/005053
申请日：2007-10-16
申请人： KOREA ATOMIC ENERGY RESEARCH INSTITUTE , KOREA HYDRO & NUCLEAR POWER CO., LTD , HONG, SER GI , KIM, YEONG-IL , KIM, SANG JI , HAHN, DO-HEE
发明人： HONG, SER GI , KIM, YEONG-IL , KIM, SANG JI , HAHN, DO-HEE
IPC分类号： G21C1/02
CPC分类号： G21C1/022 , G21C3/04 , G21C5/02 , G21C7/005 , G21Y2002/304 , G21Y2004/30 , Y02E30/34 , Y02E30/35 , Y02E30/39
摘要： A liquid-metal cooled fast reactor core having a nuclear fuel assembly constituted of nuclear fuel rods with varying cladding thicknesses in reactor core regions, in which: the nuclear fuel assembly (1) of a liquid-metal cooled fast reactor includes nuclear fuel assemblies (1a, 1b and 1c) in inner, middle and outer reactor core regions, respectively, and is installed in a hexagonal duct (3) with nuclear fuel materials (2-2a, 2-2b and 2-2c) surrounded by respective claddings (2-la, 2-lb and 2-lc), and the claddings (2-1a, 2-1b and 2-1c) of a nuclear fuel rod (2a) in the inner reactor core region, a nuclear fuel rod (2b) in the middle reactor core region and a nuclear fuel rod (2c) in the outer reactor core region are formed at different thicknesses. The reactor core can flatten power distribution using a single-enrichment nuclear fuel in the liquid-metal cooled fast reactor.
摘要翻译：一种液态金属冷却的快堆，其具有核燃料组件，该核燃料组件由反应堆核心区域中具有不同包层厚度的核燃料棒组成，其中：液态金属冷却的快堆的核燃料组件（1）包括核燃料组件 1a，1b和1c）分别安装在内，中，外反应堆堆芯区域内，并安装在由各种包层围绕的核燃料材料（2-2a，2-2b和2-2c）的六边形管道（3） 2-1a，2-lb和2-lc）和核反应堆核心区域中的核燃料棒（2a）的包层（2-1a，2-1b和2-1c），核燃料棒（2b ）和外反应堆芯区域中的核燃料棒（2c）形成为不同的厚度。反应堆堆芯可以在液态金属冷却的快速反应堆中使用单一浓缩核燃料来平坦化配电。

5. 发明申请

WO2011049290A2 INTEGRITY ASSESSMENT METHOD FOR A NUCLEAR REACTOR VESSEL 审中-公开
标题翻译：一种核反应堆容器的完整性评估方法
公开(公告)号：WO2011049290A2
公开(公告)日：2011-04-28
申请号：PCT/KR2010005692
申请日：2010-08-25
申请人： KOREA HYDRO NUCLEAR POWER CO LTD , SHIN HYE-YOUNG , NA KYUNG-HWAN , PARK YOUNG-SHEOP
发明人： SHIN HYE-YOUNG , NA KYUNG-HWAN , PARK YOUNG-SHEOP
IPC分类号： G21C17/01
CPC分类号： G21C17/01 , G01N3/42 , G01N2203/0296
摘要： The present invention primarily relates to an integrity assessment method for a nuclear reactor vessel, comprising the steps of: a) selecting main portions for hardness measurement on a surface base material within a nuclear reactor vessel tube sheet, and specific points of the base material for hardness measurement; b) selecting main portions for hardness measurement at linear welded portions of the nuclear reactor vessel, and specific points of welded portions for hardness measurement; c) selecting backup main portions and backup specific points of linear welded portions, other than the linear welded portions including the main portions selected for hardness measurement in step b), for hardness measurement; d) measuring the hardness of the specific points of the base material for hardness measurement, the specific points of the welded portions for hardness measurement, and the backup specific points, which have been selected in steps a), b), and c); and e) analyzing the results of the hardness measurements and assessing the integrity of the nuclear reactor vessel. The thus-configured method of the present invention is capable of quantitatively assessing the effects of neutron irradiation embrittlement on a nuclear reactor vessel by measuring hardness with minimal effort, while maintaining the integrity of the nuclear reactor vessel at a site, wherein the assessment results can be used to extend the operating life of the nuclear reactor vessel.
摘要翻译：本发明主要涉及一种用于核反应堆容器的完整性评估方法，该方法包括以下步骤：a）选择核反应堆容器管板内的表面基底材料上的硬度测量的主要部分，以及用于硬度测量; b）选择核反应堆容器的线性焊接部分处的硬度测量的主要部分以及用于硬度测量的焊接部分的特定点; c）选择除包括步骤b）中选择用于硬度测量的主要部分的线性焊接部分之外的线性焊接部分的备份主要部分和备用特定点以进行硬度测量; d）测量在步骤a），b）和c）中选择的用于硬度测量的基材的特定点的硬度，用于硬度测量的焊接部分的特定点以及备用特定点; 和e）分析硬度测量结果并评估核反应堆容器的完整性。如此配置的本发明的方法能够通过以最小的努力测量硬度来定量评估中子辐照脆化对核反应堆容器的影响，同时保持核反应堆容器在一个地点的完整性，其中评估结果可以用于延长核反应堆容器的使用寿命。

6. 发明申请

WO2010064740A1 APPARATUS AND METHOD FOR AUTOMATICALLY AND REMOTELY MEASURING THE INTERNAL GAP OF A REACTOR 审中-公开
标题翻译：用于自动和远程测量反应器内部空间的装置和方法
公开(公告)号：WO2010064740A1
公开(公告)日：2010-06-10
申请号：PCT/KR2008/007095
申请日：2008-12-01
申请人： KOREA HYDRO & NUCLEAR POWER CO., LTD. , LEE, Jae Gon , KANG, Yong Chul , KO, Do Young , SHIN, Jae Taek
发明人： LEE, Jae Gon , KANG, Yong Chul , KO, Do Young , SHIN, Jae Taek
IPC分类号： G21C17/10 , G21C17/08
CPC分类号： G21C17/10 , G01B7/14 , G21C13/02 , G21C19/207
摘要： The present invention relates to a remote, precise gap-measuring apparatus for automatically measuring the gap between reactor internals comprising a nuclear reactor vessel, a core support barrel, a core shroud and a lower support structure, the remote, precise gap-measuring apparatus comprising one and more digital probes measuring a gap between a nuclear reactor vessel protrusion and a core support barrel protrusion, the nuclear reactor vessel protrusions being disposed on an inner surface of the nuclear reactor vessel, the core support barrel protrusions being disposed on an outer surface of the core support barrel and engaged with the nuclear reactor vessel protrusions; a computer coupled to the digital probes to display and store a measured value of the gap measured by the digital probes; and a solenoid valve controlled by the computer, the solenoid valve controlling compressed air supplied through an air hose to operate the digital probe, wherein the digital probes measure the gap after the core support barrel, the core shroud and the lower support structure are welded to each other, thereby decreasing the construction period and simplifying the construction process.
摘要翻译：本发明涉及一种用于自动测量反应堆内部之间的间隙的远程精确的间隙测量装置，其包括核反应堆容器，芯支撑筒，芯护罩和下支撑结构，该远程精确的间隙测量装置包括一个或多个数字探头，测量核反应堆容器突起和核心支撑筒凸起之间的间隙，核反应堆容器突起设置在核反应堆容器的内表面上，芯支撑筒凸起设置在核心支撑桶并与核反应堆容器突起接合; 耦合到数字探头的计算机，显示和存储由数字探针测量的间隙的测量值; 以及由计算机控制的电磁阀，电磁阀控制通过空气软管供应的压缩空气以操作数字探头，其中数字探头在芯支撑筒之后测量间隙，将芯护罩和下支撑结构焊接到从而减少施工周期，简化施工过程。

7. 发明申请

WO2008069426A1 HIGH TEMPERATURE AND HIGH PRESSURE CORROSION RESISTANT PROCESS HEAT EXCHANGER FOR A NUCLEAR HYDROGEN PRODUCTION SYSTEM 审中-公开
标题翻译：一种核氢生产系统的高温高压耐腐蚀工艺热交换器
公开(公告)号：WO2008069426A1
公开(公告)日：2008-06-12
申请号：PCT/KR2007/004939
申请日：2007-10-10
申请人： KOREA ATOMIC ENERGY RESEARCH INSTITUTE , KOREA HYDRO & NUCLEAR POWER CO., LTD. , KIM, Yongwan , PARK, Jaewon , KIM, Minhwan , HONG, Sungdeok , LEE, Wonjae , CHANG, Jonghwa
发明人： KIM, Yongwan , PARK, Jaewon , KIM, Minhwan , HONG, Sungdeok , LEE, Wonjae , CHANG, Jonghwa
IPC分类号： G21D9/00
CPC分类号： G21D9/00 , C01B3/06 , F28D9/0062 , F28D15/00 , F28F3/025 , F28F19/02 , F28F21/08 , Y02E60/364
摘要： A high-temperature and high-pressure corrosion-resistant process heat exchanger for a nuclear hydrogen production system decomposes sulfite (SO 3 ) using heat from a high-temperature gas-cooled reactor to thereby produce sulfide (SO 2 ) and oxygen (O 2 ). The process heat exchanger comprises second and third system coolant channels, each of which is defined by a heat transmission fin, which is bent in a quadrilateral shape, and heat transmission plates, and has increased corrosion resistance thanks to ion-beam coating and ion-beam mixing using a material having high corrosion resistance. The third system coolant channel includes reaction catalysts for SO 3 decomposition, and is made of a super alloy. Thus, a system differential pressure between the second and third system coolant channels can be greatly maintained at a high temperature of 900°C or higher.
摘要翻译：用于核氢生产系统的高温和高压耐腐蚀工艺热交换器使用来自高温气冷反应堆的热分解亚硫酸盐（SO 3 N 3），从而产生硫化物（SO 2 O 2）和氧（O 2 H 2）。过程热交换器包括第二和第三系统冷却剂通道，每个通道由四边形弯曲的传热翅片和传热板限定，并且由于离子束涂覆和离子束涂覆而具有增加的耐腐蚀性，使用具有高耐腐蚀性的材料进行光束混合。第三系统冷却剂通道包括用于SO 3分解的反应催化剂，并且由超级合金制成。因此，可以在900℃以上的高温下极大地维持第二和第三系统冷却剂通道之间的系统压差。

8. 发明申请

WO2007043762A1 A NEUTRON COINCIDENCE COUNTER FOR NON-DESTRUCTIVE ACCOUNTING FOR NUCLEAR MATERIAL AND THE HANDLING METHOD THEREOF 审中-公开
标题翻译：核材料非破坏性会计核算计数器及其处理方法
公开(公告)号：WO2007043762A1
公开(公告)日：2007-04-19
申请号：PCT/KR2006/003941
申请日：2006-09-29
申请人： KOREA ATOMIC ENERGY RESEARCH INSTITUTE , KOREA HYDRO & NUCLEAR POWER CO., LTD , LEE, Tae Hoon , KIM, Ho Dong , KO, Won Il , SONG, Dae Yong , JEONG, Joong Hwan , LEE, Sang Yoon
发明人： LEE, Tae Hoon , KIM, Ho Dong , KO, Won Il , SONG, Dae Yong , JEONG, Joong Hwan , LEE, Sang Yoon
IPC分类号： G21K1/00
CPC分类号： G01T3/00 , G01T7/02
摘要： A neutron coincidence counter for non-destructive accounting for a nuclear material according to the present invention comprises an outer case, neutron detectors mounted in the outer case while being surrounded by a moderator, and a basket horizontally movable in the outer case so as to be exposed outside the outer case and having a cavity for receiving a sample container therein. Further, a neutron coincidence counter for non-destructive accounting for a nuclear material according to the present invention comprises an outer case, neutron detectors mounted in the outer case while being surrounded by a moderator, a basket movable in the outer case so as to be exposed outside the outer case and having a cavity for receiving a sample container therein, and an external signal analyzer connected to the detectors through an electrically conductive path. Moreover, at least one facile connector of one-touch connection type is mounted on the electrically conductive path for connecting the detectors to the external signal analyzer, resulting in free removal and replacement of wires connected to the connector.
摘要翻译：根据本发明的用于核材料的非破坏性核算的中子重合计数器包括外壳，安装在外壳中并由主体包围的中子探测器和可在外壳中水平移动的篮状物暴露在外壳外部并且具有用于在其中接收样品容器的空腔。此外，根据本发明的用于核材料的非破坏性核算的中子重合计数器包括外壳，安装在外壳中同时由调节器包围的中子探测器，可在外壳中移动的篮状物暴露在外壳外部并且具有用于在其中接收样品容器的空腔和通过导电路径连接到检测器的外部信号分析器。此外，至少一个轻触式连接器的简单连接器安装在导电路径上，用于将检测器连接到外部信号分析仪，从而免除了去除和更换连接到连接器的电线。

9. 发明申请

WO2010061995A1 APPARATUS AND METHOD FOR TAPPING MELTS IN PLASMA TORCH MELTER 审中-公开
标题翻译：用于在等离子体转筒中打磨梅花的装置和方法
公开(公告)号：WO2010061995A1
公开(公告)日：2010-06-03
申请号：PCT/KR2008/007101
申请日：2008-12-02
申请人： KOREA HYDRO & NUCLEAR POWER CO., LTD. , ADVANCED PLASMA TECHNOLOGY, INC. , MOON, Young Pyo , PARK, Jong Kil , HWANG, Tae Won , MOON, Chan Kook , HWANG, Soon Mo , KIM, Young Suk , DO, Chul Jin
发明人： MOON, Young Pyo , PARK, Jong Kil , HWANG, Tae Won , MOON, Chan Kook , HWANG, Soon Mo , KIM, Young Suk , DO, Chul Jin
IPC分类号： F27D15/00
CPC分类号： F27B17/00 , C21C5/5205 , F27D3/1509 , F27D99/0006 , Y02P10/216
摘要： The present invention relates to an apparatus for tapping melts, the apparatus being used for a plasma torch melter including a tapping tunnel disposed to be sloped on an area of the inner wall of a melter, a plasma torch disposed on the upper part of the melter and a main electrode disposed on the lower part of the melter to be electrically coupled with an anode of the plasma torch, the apparatus comprising: a tapping-inducing electrode electrically coupled with the main electrode in parallel, the tapping-inducing electrode being moved adjacent to the melts in the tapping tunnel, thereby being electrically coupled with the anode of the plasma torch, heating and melting the melts which remain in the tapping tunnel; a controller electrically decoupling the anode of the plasma torch with the main electrode, the controller electrically coupling the anode of the plasma torch with the tapping-inducing electrode; and a transporting device moving the tapping- inducing electrode in the tapping tunnel, thereby controlling the distance between the tapping-inducing electrode and the melts.
摘要翻译：本发明涉及一种用于分流熔体的装置，该装置用于等离子体焰炬熔化器，其包括设置成在熔化器内壁的一个区域上倾斜的攻丝通道，设置在熔化器上部的等离子体焰炬以及设置在所述熔化器的下部以与所述等离子体焰炬的阳极电耦合的主电极，所述设备包括：与所述主电极并联电耦合的出料诱导电极，所述出料诱导电极相邻移动到达攻丝隧道中的熔体，从而与等离子体焰炬的阳极电耦合，加热和熔化保留在攻丝隧道中的熔体; 所述控制器将所述等离子体焰炬的阳极与所述主电极电耦合，所述控制器将所述等离子体焰炬的阳极与所述分接诱导电极电耦合; 以及输送装置，使分接诱导电极移动到攻丝隧道内，从而控制出料诱导电极与熔体之间的距离。

10. 发明申请

WO2010058880A1 TEST APPARATUS AND METHOD FOR SAFETY VALVE 审中-公开
标题翻译：安全阀的测试装置和方法
公开(公告)号：WO2010058880A1
公开(公告)日：2010-05-27
申请号：PCT/KR2009/000040
申请日：2009-01-06
申请人： KOREA HYDRO & NUCLEAR POWER CO., LTD. , OH, Seung-jong , JERNG, Dong-wook , PARK, Jong-woon , KWON, Kab-ju , KIM, Chang-hyun
发明人： OH, Seung-jong , JERNG, Dong-wook , PARK, Jong-woon , KWON, Kab-ju , KIM, Chang-hyun
IPC分类号： G01M13/00
CPC分类号： G01M13/005
摘要： An apparatus and method for testing the performance of a safety valve perform tests under the same operation conditions as a pressurizer safety valve installed on a reactor coolant system of a nuclear power plant. The apparatus for testing the performance of a safety valve, i.e., a set pressure test, a seat tightness test, a flow rate test, a blow-down test, a water discharge test of a loop seal, a discharge load test, etc. on the safety valve, includes an accumulator 21 including at least one electric heater 22 for heating a predetermined amount of water filled therein, and storing steam produced by the electric heater 22 under high pressure, a test vessel 41 storing the steam supplied from the accumulator 21 under high pressure, and providing test pressure to a subject safety valve 48, the steam being supplied after flow rate and pressure thereof are controlled, a condensing tank 81 storing demineralized water to be supplied to the accumulator 21, and condensing and collecting the steam discharged from the subject safety valve 48, and a water-supply pump 111 supplying the water stored in the condensing tank 81 to the accumulator 21.
摘要翻译：用于测试安全阀的性能的装置和方法在与安装在核电站的反应堆冷却剂系统上的加压器安全阀相同的操作条件下进行测试。用于测试安全阀性能的装置，即设定压力试验，阀座密封性试验，流量试验，吹扫试验，环形密封的排水试验，放电载荷试验等。在安全阀上设置有包括至少一个用于加热预定量的水的电加热器22并且在高压下储存由电加热器22产生的蒸汽的蓄电器21，存储从蓄电池供给的蒸汽的测试容器41 21，并且对被检查体安全阀48提供试验压力，控制其流量和压力后供给的蒸汽;储存供给蓄能器21的软化水的冷凝罐81，并将蒸汽冷凝并收集从主体安全阀48排出的供水泵111以及将蓄冷器81中存储的水供给蓄能器21的供水泵111。

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