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71. 发明申请

US20140093025A1 ARRANGEMENT AND METHOD FOR PROVIDING AN EMERGENCY SUPPLY TO A NUCLEAR INSTALLATION 有权
标题翻译：向紧急情况提供核设施的安排和方法
公开(公告)号：US20140093025A1
公开(公告)日：2014-04-03
申请号：US14123239
申请日：2012-05-30
申请人： 123-ENGINEERING LTD. & CO. KG
发明人： Frank Mekiska
IPC分类号： G21C15/18 , G21D1/04 , G21D3/06 , G21D1/02
CPC分类号： G21C15/182 , F02B63/04 , G21D1/02 , G21D1/04 , G21D3/06 , Y02E30/40
摘要： The invention relates to a method and an arrangement for providing an emergency supply to a nuclear installation. The arrangement comprises a container (10) with a plurality of permanently installed devices and at least one motor (22), one generator (26), one pump (24), one fuel tank (14) and one transformer (34), wherein the pump and the generator are functionally connected to the motor in order to activate said motor.
摘要翻译：本发明涉及一种向核设备提供紧急供应的方法和装置。该装置包括具有多个永久安装的装置和至少一个马达（22），一个发电机（26），一个泵（24），一个燃料箱（14）和一个变压器（34）的容器（10），其中泵和发电机功能上连接到电动机以激活所述电动机。

72. 发明申请

US20140029711A1 PASSIVE POWER PRODUCTION DURING A NUCLEAR STATION BLACKOUT 有权
标题翻译：核电站黑洞期间的被动电力生产
公开(公告)号：US20140029711A1
公开(公告)日：2014-01-30
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
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 Sterling 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。

73. 发明申请

US20130301782A1 DEFENSE IN DEPTH SAFETY PARADIGM FOR NUCLEAR REACTOR 审中-公开
标题翻译：核反应堆深度安全示范防御
公开(公告)号：US20130301782A1
公开(公告)日：2013-11-14
申请号：US13864053
申请日：2013-04-16
申请人： Babcock & Wilcox mPower, Inc.
发明人： JOHN D. MALLOY, III
IPC分类号： G21C15/18 , G21C9/004
CPC分类号： G21C15/18 , G21C1/32 , G21C9/004 , G21C9/02 , G21D3/06 , Y02E30/40
摘要： A nuclear reactor includes a nuclear reactor core disposed in a pressure vessel and immersed in primary coolant water at an operating pressure higher than atmospheric pressure. A containment structure contains the nuclear reactor. A reactor coolant inventory and purification system (RCI) is connected with the pressure vessel by make-up and letdown lines. The RCI includes a high pressure heat exchanger configured to operate responsive to a safety event at the operating pressure to remove heat from the primary coolant water in the pressure vessel. An auxiliary condenser located outside containment also removes heat. The RCI also includes a pump configured to inject make up water into the pressure vessel via the make-up line against the operating pressure. An emergency core cooling system (ECC) operates to depressurize the nuclear reactor only if the RCI and auxiliary condenser are unable to manage the safety event.
摘要翻译：核反应堆包括设置在压力容器中并在高于大气压的操作压力下浸入主冷却水中的核反应堆堆芯。遏制结构包含核反应堆。反应堆冷却剂库存和净化系统（RCI）通过化妆和排料线与压力容器连接。 RCI包括高压热交换器，其被配置为响应于在操作压力下的安全事件来操作以从压力容器中的一级冷却水排出热量。位于安全壳外部的辅助冷凝器还消除热量。 RCI还包括配置成经由化妆线将补充水抵抗工作压力注入到压力容器中的泵。只有当RCI和辅助冷凝器不能管理安全事件时，应急核心冷却系统（ECC）才能使核反应堆减压。

74. 发明申请

US20120314830A1 INSTALLATION FOR PRODUCING POWER FROM A GAS-COOLED FAST NUCLEAR REACTOR 审中-公开
标题翻译：从气体冷却的快速核反应堆生产电力的安装
公开(公告)号：US20120314830A1
公开(公告)日：2012-12-13
申请号：US13581162
申请日：2011-02-23
申请人： Nicolas Tauveron , Fabrice Bentivoglio
发明人： Nicolas Tauveron , Fabrice Bentivoglio
IPC分类号： G21C15/253
CPC分类号： G21D3/06 , F02C1/05 , G21C1/028 , G21C15/18 , G21C15/28 , Y02E30/33 , Y02E30/34
摘要： A power production installation including a primary circuit containing gas passing via a nuclear reactor, via a first heat exchanger, and via a blower. A secondary circuit containing incondensable gas passes via the first heat exchanger, and via a turbine and a compressor fitted on the same shaft. The blower is driven by the shaft. The gases in the primary and secondary circuits are of the same nature, and the pressure in the secondary circuit is automatically regulated by the pressure in the primary circuit.
摘要翻译：一种发电装置，包括通过第一热交换器和经由鼓风机的经由核反应堆通过气体的初级回路。含有不可冷凝气体的二次回路经由第一热交换器，经由安装在同一轴上的涡轮机和压缩机通过。鼓风机由轴驱动。初级和次级回路中的气体性质相同，二级回路中的压力由主回路中的压力自动调节。

75. 发明申请

US20120263268A1 PASSIVE HIGH PRESSURE SAFETY INJECTION TANK SYSTEM (HPSIT) FOR RESPONDING TO STATION BLACKOUT (SBO) AND LOSS-OF-COOLANT ACCIDENTS (LOCA) 有权
标题翻译：被动高压安全注射罐系统（HPSIT），用于响应站点黑色（SBO）和失物事件（LOCA）
公开(公告)号：US20120263268A1
公开(公告)日：2012-10-18
申请号：US13189871
申请日：2011-07-25
申请人： Tae-Soon Kwon , Dong-Jin Euh , Chul-Hwa Song , Won-Pil Baek
发明人： Tae-Soon Kwon , Dong-Jin Euh , Chul-Hwa Song , Won-Pil Baek
IPC分类号： G21C9/00
CPC分类号： G21C15/18 , G21D3/06 , Y02E30/40
摘要： A high pressure safety injection tank (HPSIT) system includes one safety injection tank (HIT) which replaces a core makeup tank (CMT) and a low pressure (approximately 4.3 Mpa or below) safety injection tank (SIT) and which can shift to and operate on a high pressure (approximately 17 Mpa) operation mode, to enable injection of emergency core coolant into a reactor system both under low pressure (approximately 4.3 Mpa or below) and high pressure (approximately 17 Mpa).
摘要翻译：高压安全注射罐（HPSIT）系统包括一个安全注射罐（HIT），可替代核心化妆池（CMT）和低压（约4.3 Mpa或更低）安全注射罐（SIT），并可将其转移到在高压（约17Mpa）的操作模式下操作，以便在低压（约4.3Mpa或更低））和高压（约17Mpa）下将应急芯冷却剂注入反应堆系统。

76. 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。

77. 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。

78. 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）。

79. 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。

80. 发明公开

US20230368934A1 Method for analyzing severe accident in nuclear reactor based on advanced particle method 审中-公开
公开(公告)号：US20230368934A1
公开(公告)日：2023-11-16
申请号：US18213904
申请日：2023-06-26
申请人： XI`AN JIAOTONG UNIVERSITY
发明人： Ronghua Chen , Qinghang Cai , Kailun Guo , Wenxi Tian , Guanghui Su , Suizheng Qiu
IPC分类号： G21D3/06 , G21D3/00
CPC分类号： G21D3/06 , G21D3/005
摘要： A method for analyzing a sever accident in a nuclear reactor based on an advanced particle method includes steps of: 1) performing geometric modeling, setting initial conditions and boundary conditions; 2) updating material physical properties and key parameters; 3) performing mechanical structure module calculation, updating solid particle stress, strain, internal energy, displacement and velocity; 4) performing thermal hydraulic module calculation, updating fluid particle internal energy, position and velocity; 5) performing chemical reaction module calculation, updating particle matter composition and internal energy; 6) performing neutron physics module calculation, updating particle neutron flux density; and 7) outputting data. The method of the present invention is based on the discrete form of the advanced particle method, which is capable of accurately capturing cross-sectional changes, matter changes, and phase changes. Compared with grid method, the present invention can effectively avoid a mesh distortion problem existing in a large deformation.

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