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81. 发明授权

US10504627B2 Method for managing stoppage of a pressurised-water nuclear reactor 有权
公开(公告)号：US10504627B2
公开(公告)日：2019-12-10
申请号：US15536078
申请日：2015-12-16
申请人： DCNS
发明人： Jean Masdupuy , Fabien Puccetti , Geoffrey Paul Etienne Haratyk , Vincent Gourmel
IPC分类号： G21C15/18 , G21D3/06 , G21C19/28 , G21D1/00 , G21D3/00
CPC分类号： G21C15/18 , G21C19/28 , G21D1/006 , G21D3/06 , G21D3/001 , Y02E30/40
摘要： Disclosed is a method for managing stoppage of a pressurized-water nuclear reactor integrated into a submerged module for producing electrical power, in case of detection of a primary/secondary leak in a steam generator equipped with a safety valve, which generator is connected to the reactor and associated with a standby cooling unit. The method includes: detecting a primary/secondary leak in the steam generator; automatically stopping the reactor and isolating the broken steam generator; bringing the corresponding standby cooling unit online; monitoring the primary pressure and, once the primary pressure has passed below the set pressure of the safety valves of the steam generators, isolating the standby cooling unit of the broken steam generator; and continuing to passively cool the reactor with the remaining steam generators and cooling unit.

82. 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.

83. 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.

84. 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.

85. 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.

86. 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.

87. 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。

88. 发明授权

US09536629B2 Passive power production during a nuclear station blackout 有权
标题翻译：核电站停电期间的无源电力生产
公开(公告)号：US09536629B2
公开(公告)日：2017-01-03
申请号：US13764804
申请日：2013-02-12
申请人： Westinghouse Electric Company LLC
发明人： Jeffrey T. Dederer , Catherine M. Perego
IPC分类号： G21C15/18 , G21D3/06 , G21C15/26
CPC分类号： G21C15/18 , G21C15/26 , G21D3/06 , Y02E30/40
摘要： Apparatus for passively generating electric power during a nuclear power station blackout by utilizing the temperature difference between the hot inlet of a residual heat removal circuit and the surrounding containment environment. A heat engine, such as a thermoelectric generator, a Stirling Cycle Engine or Rankine Cycle Engine, is coupled in heat exchange relationship with an uninsulated portion of the inlet to a passive residual heat removal heat exchanger and/or passive residual heat removal heat exchanger channel head to generate the power required to operate essential equipment needed to maintain the nuclear power station in a safe condition during a loss of normal onsite and offsite power.
摘要翻译：利用残余除热电路的热入口与周围的容纳环境之间的温度差，在核电站停电期间被动发电的装置。诸如热电发电机，斯特林循环发动机或兰金循环发动机的热力发动机以与入口的未绝缘部分的热交换关系耦合到被动余热除热器和/或被动余热除热器通道负责在正常的现场和异地电力损失的情况下产生维持核电站处于安全状态所需的基本设备所需的电力。

89. 发明申请

US20160358676A1 HYDRAULIC CONTROL UNIT AND METHOD OF SHUTTING DOWN A NUCLEAR REACTOR USING THE SAME 有权
标题翻译：液压控制单元以及使用该方法切断核反应堆的方法
公开(公告)号：US20160358676A1
公开(公告)日：2016-12-08
申请号：US14565819
申请日：2014-12-10
申请人： Kenneth Allan MORGAN , Filemon Tecson CABRERA , Randy Morris BROWN
发明人： Kenneth Allan MORGAN , Filemon Tecson CABRERA , Randy Morris BROWN
IPC分类号： G21C7/16 , G21C9/02 , G21C7/36 , G21D3/06
CPC分类号： G21C7/16 , F15B1/022 , F15B1/103 , F15B2201/205 , F15B2201/3153 , G21C7/08 , G21C7/36 , G21C9/02 , G21D3/06 , G21Y2002/40 , G21Y2004/30 , Y02E30/40
摘要： A method of shutting down a nuclear reactor may include compressing a scram gas that is in fluid communication with a scram accumulator. The scram accumulator defines a chamber therein and contains bellows within the chamber. The bellows are configured to hold a scram liquid in isolation of the scram gas. The scram gas exerts a compressive force on the bellows in a form of stored energy. The method may additionally include releasing the stored energy in response to a scram signal such that the scram gas expands into the chamber of the scram accumulator to compress the bellows and expel the scram liquid from the scram accumulator to insert control rods into a core of the nuclear reactor.
摘要翻译：关闭核反应堆的方法可以包括压缩与冲击式蓄能器流体连通的冲击气体。冲击蓄能器在其中限定一个室，并在室内包含波纹管。波纹管被配置为保持隔离气流的冲击液。冲击气体以存储能量的形式在波纹管上施加压缩力。该方法可以另外包括响应于扰流信号释放所存储的能量，使得所述扰流气体扩展到所述冲击累加器的室中以压缩所述波纹管并将所述冲击液体从所述冲击累加器排出以将控制棒插入所述核反应堆。

90. 发明授权

US09460818B2 Low pressure reactor safety systems and methods 有权
标题翻译：低压反应堆安全系统和方法
公开(公告)号：US09460818B2
公开(公告)日：2016-10-04
申请号：US13425985
申请日：2012-03-21
申请人： Mark A. Bergman
发明人： Mark A. Bergman
IPC分类号： G21C9/00 , G21D1/02 , G21C15/18 , G21D3/06
CPC分类号： G21D1/02 , G21C15/18 , G21C2015/185 , G21D3/06 , Y02E30/31
摘要： A supplementary injection device is installed in a nuclear power plant to draw coolant and inject coolant using an entraining fluid. The injection device can be a venturi or other passive device operable at relatively low fluid pressure that draws coolant through suction at the venturi narrowing point and mixes the coolant with the fluid for injection. The injection device is operable with a known BWR design, where the device is attached to a steam connection to the main steam line of the reactor, a coolant connection drawing from suction lines to a suppression cool or condensate tank, and an outlet connection injecting into the main feedwater lines. In a BWR, the injection device is operable without electricity and at a wide range of pressures, even less than 50 pounds per square inch, to maintain coolant levels in the reactor.
摘要翻译：一个补充注射装置安装在核电站中以吸引冷却液并使用夹带流体注入冷却剂。注射装置可以是文丘里管或其他无源装置，其在相对较低的流体压力下可操作，其通过吸入文丘里变窄点的冷却剂并将冷却剂与注射用流体混合。注射装置可以用已知的BWR设计操作，其中装置连接到与反应堆的主蒸汽管线的蒸汽连接，从吸入管线到抑制冷或冷凝罐的冷却剂连接，以及注入到主要给水线。在BWR中，注射装置可在没有电的情况下操作，并且在甚至小于50磅/平方英寸的宽范围的压力下操作，以保持反应器中的冷却剂水平。

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