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71. 发明申请

US20050201507A1 Nuclear power plant, method of replacement in the same and method of operating the same 有权
标题翻译：核电厂，替代方法和操作方法相同
公开(公告)号：US20050201507A1
公开(公告)日：2005-09-15
申请号：US11032289
申请日：2005-01-10
申请人： Masashi Sugiyama , Yukihiro Katayama , Kenji Tominaga , Hirohisa Satomi , Ichirou Shimoda
发明人： Masashi Sugiyama , Yukihiro Katayama , Kenji Tominaga , Hirohisa Satomi , Ichirou Shimoda
IPC分类号： G21C7/26 , G21C9/00 , G21C15/243 , G21D3/04
CPC分类号： G21D3/06 , G21C9/00 , Y02E30/40
摘要： A recirculation pump motor is supplied with a power from a unit auxiliary middle voltage bus through a power supply system including a first circuit breaker, a voltage source inverter, and a second circuit breaker electrically connected in series to provide a no-load operation by use of the voltage source inverter. The second circuit breaker may be multiplexed with more than one breaker electrically connected in series. An existing nuclear plant using a induction motor driving a hydraulic coupling mechanically coupled to a synchronous generator for driving the recirculation pump, such as an MfG set, may be subjected to a method of replacing the induction motor, the hydraulic coupling, and the synchronous generator with the voltage source inverter and a circuit breaker through electrically disconnection and removal.
摘要翻译：循环泵电动机通过包括第一断路器，电压源逆变器和电连接在一起的第二断路器的电源系统从单元辅助中压电压总线供电，以提供使用中的空载操作的电压源逆变器。第二断路器可与多于一个断路器进行多路复用，该断路器串联电连接。使用驱动液压联轴器的感应电动机的现有核电厂可以采用一种替代感应电动机，液压联轴器和同步发电机的方法，所述异步电动机机械耦合到同步发电机以驱动诸如MfG组的再循环泵与电源逆变器和断路器通过电气断开和拆卸。

72. 发明授权

US06859757B2 Complex article tagging with maintenance related information 有权
标题翻译：复杂的文章标签与维护相关的信息
公开(公告)号：US06859757B2
公开(公告)日：2005-02-22
申请号：US10210202
申请日：2002-07-31
申请人： Gordon Muehl , Klaus Irle , Walter G. Kienle , Knut Heusermann
发明人： Gordon Muehl , Klaus Irle , Walter G. Kienle , Knut Heusermann
IPC分类号： G06Q10/06 , G21D3/06 , G21D5/02 , G06F19/00 , G01M17/00
CPC分类号： G21D5/02 , G06Q10/06 , G21D3/06
摘要： A method for maintaining a complex article, including retrieving maintenance information relating to maintenance of a component of a complex article from an electronically-accessible tag coupled to the component and applying the retrieved maintenance information to a determination regarding maintenance of the complex article. A device including a complex article including a first component and a second component, the first and second components being one of individually replaceable and maintainable. The first component is tagged with a first tag that stores first computer accessible information including a first identifier identifying the first component and first maintenance information describing maintenance of the first component. The second component is tagged with a second tag that stores second computer accessible information including a second identifier identifying the second component and second maintenance information describing maintenance of the second component.
摘要翻译：一种用于维护复杂物品的方法，包括从耦合到所述部件的电子可访问标签检索与复杂物品的部件的维护有关的维护信息，以及将所检索的维护信息应用于关于所述复杂物件的维护的确定。一种包括复合制品的装置，包括第一部件和第二部件，所述第一和第二部件是可单独替换和可维护的部件之一。第一组件被标记有第一标签，其存储第一计算机可访问信息，包括识别第一组件的第一标识符和描述第一组件的维护的第一维护信息。第二组件被标记有第二标签，其存储第二计算机可访问信息，包括标识第二组件的第二标识符和描述第二组件的维护的第二维护信息。

73. 发明授权

US4421716A Safety monitoring and reactor transient interpreter 失效
标题翻译：安全监控和反应堆瞬态解释器
公开(公告)号：US4421716A
公开(公告)日：1983-12-20
申请号：US221327
申请日：1980-12-29
申请人： John E. Hench , Tom Y. Fukushima
发明人： John E. Hench , Tom Y. Fukushima
IPC分类号： G21D3/06 , G21C7/36
CPC分类号： G21D3/06 , Y02E30/40
摘要： An apparatus which monitors a subset of control panel inputs in a nuclear reactor power plant, the subset being those indicators of plant status which are of a critical nature during an unusual event. A display (10) is provided for displaying primary information (14) as to whether the core is covered and likely to remain covered, including information as to the status of subsystems needed to cool the core and maintain core integrity. Secondary display information (18, 20) is provided which can be viewed selectively for more detailed information when an abnormal condition occurs. The primary display information has messages (24) for prompting an operator as to which one of a number of pushbuttons (16) to press to bring up the appropriate secondary display (18, 20). The apparatus utilizes a thermal-hydraulic analysis to more accurately determine key parameters (such as water level) from other measured parameters, such as power, pressure, and flow rate.
摘要翻译：监控核反应堆发电厂控制面板输入子集的装置，该子集是在异常事件期间具有关键性质的植物状态指标。提供显示器（10），用于显示关于核心是否被覆盖并且可能保持被覆盖的主要信息（14），包括关于冷却核心并保持核心完整性所需的子系统的状态的信息。提供二次显示信息（18,20），当出现异常情况时，可以选择性地查看更多详细信息。主要显示信息具有用于提示操作者按下多个按钮（16）中的哪一个以提起适当的辅助显示器（18,20）的消息（24）。该装置利用热液压分析来更精确地确定来自其它测量参数（诸如功率，压力和流速）的关键参数（例如水位）。

74. 发明授权

US4096881A Nuclear-reactor steam-generator shut-off valve 失效
标题翻译：核反应堆蒸汽发生器截止阀
公开(公告)号：US4096881A
公开(公告)日：1978-06-27
申请号：US590674
申请日：1975-06-26
申请人： Hans-Peter Schabert , Erwin Laurer
发明人： Hans-Peter Schabert , Erwin Laurer
IPC分类号： G05D16/14 , G21C9/00 , G21D3/04 , G21D3/06 , F16K31/122
CPC分类号： G21C9/00 , G05D16/14 , G21D3/04 , G21D3/06 , Y02E30/32 , Y10T137/7769
摘要： In a nuclear reactor installation, a live-steam line leading from each steam generator through the containment, is equipped with a fast-acting valve. If the pressure in the generator rises the valve operates as a safety valve and releases up to one-half of the aperture cross section of the valve, so that there is no danger of damage to the steam generators. According to the invention, the valve is operated for this purpose by two pistons by means of steam. The invention is of interest particularly for light-water reactors, e.g., pressurized-water reactors.
摘要翻译：在核反应堆安装中，从每个蒸汽发生器通过容器引出的活蒸汽管路配备有快速作用阀。如果发电机中的压力升高，阀门将作为安全阀进行操作，并释放出阀门孔径横截面的一半，这样就不会损坏蒸汽发生器。根据本发明，通过两个活塞通过蒸汽为此目的操作阀。尤其对于轻水反应器，例如加压水反应器，本发明尤其有利。

75. 发明申请

US20180330837A1 DIGITAL PROTECTION SYSTEM FOR NUCLEAR POWER PLANT 审中-公开
公开(公告)号：US20180330837A1
公开(公告)日：2018-11-15
申请号：US15970888
申请日：2018-05-04
申请人： DOOSAN HEAVY INDUSTRIES & CONSTRUCTION CO., LTD.
发明人： Sanghoon LEE , Choonyong LEE , Chaeho NAM
IPC分类号： G21D3/06 , G21C7/36 , G21C17/032 , G21D3/00 , G21D5/08 , G05B19/05
CPC分类号： G21D3/06 , G05B9/03 , G05B19/0428 , G05B19/058 , G05B2219/14006 , G05B2219/14124 , G21C7/36 , G21C17/032 , G21D3/001 , G21D5/08
摘要： A digital protection system includes a process protection system having at least two channels and a reactor protection system having at least two trains. The process protection system includes, in one channel, first and second comparative logic controllers of different types that are mutually independent of each other and that respectively receive process variables as inputs and each outputting comparison logic results. The reactor protection system includes, in one train, first and second concurrent logic controllers of different types that are mutually independent from each other and that respectively receive the comparison logic results as inputs and each outputting concurrent logic results. The reactor protection system includes initiation circuits, each circuit including a plurality of relays connected in series and a plurality of relays connected in parallel. One series-connected relay is controlled by one of the two different concurrent logic results, and one parallel-connected relay is controlled by the other.

76. 发明申请

US20180308592A1 STOPPED COOLING SYSTEM AND NUCLEAR FACILITY HAVING SAME 审中-公开
公开(公告)号：US20180308592A1
公开(公告)日：2018-10-25
申请号：US15520594
申请日：2015-10-05
申请人： KOREA ATOMIC ENERGY RESEARCH INSTITUTE
发明人： Young In KIM , Keung Koo KIM , Jae Joo HA , Tae Wan KIM , Hun Sik HAN , Kyung Jun KANG
IPC分类号： G21C15/18 , G21C1/18 , G21C1/09 , F22D11/02 , F22D5/34
CPC分类号： G21C15/182 , F01K13/025 , F22B1/162 , F22B1/1823 , F22B35/108 , F22D5/34 , F22D11/02 , G21C1/09 , G21C1/18 , G21C1/326 , G21C13/024 , G21D1/006 , G21D3/06 , Y02E30/40
摘要： The present disclosure provides a stopped cooling system including: a steam line connecting portion connected to a steam line so as to receive cooling water through the steam line connected to an outlet of a steam generator; a stopped cooling heat exchanger for receiving cooling water that enters the stopped cooling system through the steam line connecting portion, and discharging same through a passage of the heat exchanger; a stopped cooling pump activated to perform stopped cooling of the nuclear reactor upon normal stoppage of the nuclear reactor after primary cooling of the nuclear reactor cooling system or when an accident occurs, and for forming a circulating flow of cooling water that circulates between the steam generator and the stopped cooling heat exchanger; and a water supplying pipe connecting portion connected to the heat exchanger passage and a water supplying pipe, which is connected to the inlet of the steam generator, so as to supply the cooling water cooled in the stopped cooling heat exchanger to the steam generator through the water supplying pipe.

77. 发明申请

US20180190403A1 PLANT OPERATION SYSTEM AND PLANT OPERATION METHOD 审中-公开
公开(公告)号：US20180190403A1
公开(公告)日：2018-07-05
申请号：US15736547
申请日：2016-06-22
申请人： MITSUBISHI HEAVY INDUSTRIES, LTD.
发明人： Kenji Mashio , Takae Yamashita , Takashi Azuma , Susumu Shiizuka , Junichi Nishitani , Masafumi Utsumi , Jun Shibuya
IPC分类号： G21D3/06 , G05B19/05 , G21C17/00 , G21C9/00
CPC分类号： G21D3/06 , G05B19/058 , G05B23/0283 , G05B2219/161 , G05B2219/24019 , G05B2219/32226 , G21C9/00 , G21C17/00 , Y02P90/14
摘要： An atomic power plant operation system for assisting the operation of an atomic power generation plant is provided with: an operation monitoring system which monitors and controls the operation of the atomic power generation plant; an abnormality indication monitoring system which, on the basis of an operation history of the atomic power generation plant, monitors an indication of abnormality in the atomic power generation plant; an abnormality diagnosis system which, on the basis of a result of abnormality indication that has been detected, makes an abnormality diagnosis for the atomic power generation plant; and a maintenance system for performing maintenance and management of the atomic power generation plant, wherein the systems are communicably connected, and the abnormality diagnosis system provides the maintenance system with the result of the abnormality diagnosis of the atomic power generation plant.

78. 发明授权

US09911513B2 Passive shutdown system and method of operating a liquid metal cooled reactor using the same 有权
公开(公告)号：US09911513B2
公开(公告)日：2018-03-06
申请号：US14154593
申请日：2014-01-14
申请人： Eric Paul Loewen , Weston Matthew Cundiff , Pradip Saha , Derek Bass
发明人： Eric Paul Loewen , Weston Matthew Cundiff , Pradip Saha , Derek Bass
IPC分类号： G21C7/08 , G21C7/22 , G21C7/32 , G21C9/027 , G21C15/247 , G21D3/06 , G21C1/02
CPC分类号： G21C7/22 , G21C1/02 , G21C7/08 , G21C7/32 , G21C9/027 , G21C15/247 , G21D3/06 , Y02E30/35 , Y02E30/39
摘要： A passive shutdown system for a liquid metal cooled reactor may include a tube and a neutron absorber within the tube. The tube may be configured to extend through a core of the liquid metal cooled reactor. The tube has an upper end and a lower end. The tube defines a flow path for a liquid metal coolant. The neutron absorber is a mobile structure configured to partially obstruct a flow of the liquid metal coolant within the flow path. A method of operating a liquid metal cooled reactor may involve the use of the passive shutdown system.

79. 发明申请

US20170162279A1 NUCLEAR REACTOR SCRAM CONTROL SYSTEM 审中-公开
公开(公告)号：US20170162279A1
公开(公告)日：2017-06-08
申请号：US14960769
申请日：2015-12-07
申请人： John Robert BASS , Ted Gordon BAHENSKY , Sean Wilson MIERS , Robert A. AYER
发明人： John Robert BASS , Ted Gordon BAHENSKY , Sean Wilson MIERS , Robert A. AYER
IPC分类号： G21C7/16 , G21C7/36
CPC分类号： G21C7/16 , F16K37/0041 , G21C7/36 , G21C9/02 , G21C17/10 , G21D3/06 , Y02E30/39
摘要： A nuclear reactor scram control system for a nuclear reactor includes a solenoid pilot valve (SSPV). The SSPV includes a solenoid indicator light electrically coupled to an SSPV solenoid of the SSPV. The solenoid indicator light may be selectively activated based on an energization state of the SSPV solenoid, thereby providing an immediate and visually observable indication of the SSPV energization state. The immediate and visually observable indication of the SSPV energization state may enable quicker and more reliable verification of SSPV solenoid energization state. As a result, operator radiation exposure associated with verification may be reduced, and a risk of inadvertent nuclear reactor scram based on a de-energized SSPV solenoid may be reduced, thus streamlined nuclear reactor operations.

80. 发明授权

US09589683B2 Reactor shutdown system 有权
标题翻译：反应堆停机系统
公开(公告)号：US09589683B2
公开(公告)日：2017-03-07
申请号：US13296313
申请日：2011-11-15
申请人： Hiroshi Fujimoto , Hironobu Shinohara , Yasutake Akizuki , Toshiki Fukui , Yuichi Tanaka , Shinji Kiuchi , Hiroshi Shirasawa , Toshiaki Matsumura
发明人： Hiroshi Fujimoto , Hironobu Shinohara , Yasutake Akizuki , Toshiki Fukui , Yuichi Tanaka , Shinji Kiuchi , Hiroshi Shirasawa , Toshiaki Matsumura
IPC分类号： G21C9/02 , G21C9/027 , G21D3/06 , G21C7/08 , G21C7/12
CPC分类号： G21C9/02 , G21C7/08 , G21C7/12 , G21C9/027 , G21D3/06 , Y02E30/40
摘要： A reactor shutdown system includes a reactor, a control-rod drive unit that can drive a control rod in pulling and inserting directions with respect to a fuel assembly, a power source that can supply power to the control-rod drive unit, and a power converter that is provided between the control-rod drive unit and the power source, in which when power supply is cut off, the control-rod drive unit inserts the control rod into the fuel assembly to stop nuclear reaction in the reactor, and the reactor shutdown system includes a reactor trip breaker provided between the power converter and the control-rod drive unit, a safety protection-system device that controls the reactor trip breaker to cut off power supply to the control-rod drive unit, and a CCF device that controls the power converter to cut off power supply to the control-rod drive unit.
摘要翻译：反应堆关闭系统包括反应器，控制棒驱动单元，其可驱动控制杆相对于燃料组件拉动和插入方向，能够向控制棒驱动单元供电的电源，以及功率转换器，其设置在控制棒驱动单元和电源之间，其中当电源被切断时，控制杆驱动单元将控制杆插入燃料组件中以停止反应器中的核反应，并且反应器关闭系统包括设置在功率转换器和控制棒驱动单元之间的电抗器跳闸断路器，控制电抗器跳闸断路器以切断对控制杆驱动单元的电源的安全保护系统装置，以及CCF装置，控制电源转换器切断控制棒驱动单元的电源。

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