公开(公告)号：US09865364B2

公开(公告)日：2018-01-09

申请号：US14174630

申请日：2014-02-06

申请人： BWXT mPower, Inc. ,  BWXT Nuclear Operations Group, Inc.

发明人： Christopher D. Dodd ,  Paul K. DeSantis ,  Kevin J. Stambaugh ,  Allan R. Mackovjak ,  John P. McLaughlin ,  Brett T. Goodyear ,  Michael J. Edwards ,  Matthew W. Ales

IPC分类号： G21C7/14 ,  G21C7/117 ,  G21C9/02

CPC分类号： G21C7/14 ,  G21C7/117 ,  G21C9/02 ,  Y02E30/39

摘要： A control rod drive mechanism (CRDM) configured to latch onto the lifting rod of a control rod assembly and including separate latch engagement and latch holding mechanisms. A CRDM configured to latch onto the lifting rod of a control rod assembly and including a four-bar linkage closing the latch, wherein the four-bar linkage biases the latch closed under force of gravity.

公开(公告)号：US09620255B2

公开(公告)日：2017-04-11

申请号：US13326465

申请日：2011-12-15

申请人： Joseph E. Kowles ,  David A. Story

发明人： Joseph E. Kowles ,  David A. Story

IPC分类号： G21C9/02 ,  G21C17/12 ,  G01D5/251 ,  G21C7/12

CPC分类号： G21C17/12 ,  G01D5/2515 ,  G21C7/12 ,  G21C9/02 ,  Y02E30/32 ,  Y02E30/39

摘要： A high temperature reed switch position indicator for a pressurized water reactor in which the drive rod housing is completely immersed in the reactor coolant. The reed switch sensor modules positioned along the control rod drive rod travel housing are constructed solely of metallic, ceramic and glass materials and are sealed within an outer housing to isolate the sensor assembly from the coolant.

公开(公告)号：US08526563B2

公开(公告)日：2013-09-03

申请号：US12862124

申请日：2010-08-24

申请人： Scott J. Shargots ,  Mathew W. Ales

发明人： Scott J. Shargots ,  Mathew W. Ales

IPC分类号： G21C7/06

CPC分类号： G21C7/117 ,  G21C7/12 ,  G21C9/02 ,  Y02E30/39

摘要： A nuclear reactor includes a pressure vessel, and a control rod assembly (CRA) including at least one movable control rod, a control rod drive mechanism (CRDM) for controlling movement of the at least one control rod, and a coupling operatively connecting the at least one control rod and the CRDM. The coupling includes a connecting rod engaged with the CRDM and a terminal element connected with a lower end of the connecting rod and further connected with the at least one control rod. In some embodiments the terminal element includes a first portion comprising a first material having a first density and a second portion comprising a second material having a second density that is greater than the first density. In some embodiments the terminal element has a largest dimension parallel with the connecting rod that is greater than or equal to a largest dimension transverse to the connecting rod.

摘要翻译： 核反应堆包括压力容器和控制杆组件（CRA），控制杆组件（CRA）包括至少一个可移动控制杆，用于控制至少一个控制杆的运动的控制杆驱动机构（CRDM） 至少一个控制杆和CRDM。 联接器包括与CRDM接合的连杆和与连杆的下端连接并与至少一个控制杆连接的端子元件。 在一些实施例中，端子元件包括第一部分，其包括具有第一密度的第一材料，第二部分包括具有大于第一密度的第二密度的第二材料。 在一些实施例中，端子元件具有与连杆平行的最大尺寸，该尺寸大于或等于横向于连接杆的最大尺寸。

公开(公告)号：US20130114779A1

公开(公告)日：2013-05-09

申请号：US13603185

申请日：2012-09-04

申请人： Sang Jong LEE ,  Seoung Eun CHUN ,  Geol Woo LEE ,  Byeong Tae YU ,  Joon Sung KIM ,  Tae Young YOON ,  Sung Min CHOI ,  Hye Jin KIM ,  Sang Jung PARK ,  Hyoung Gun SHIM

发明人： Sang Jong LEE ,  Seoung Eun CHUN ,  Geol Woo LEE ,  Byeong Tae YU ,  Joon Sung KIM ,  Tae Young YOON ,  Sung Min CHOI ,  Hye Jin KIM ,  Sang Jung PARK ,  Hyoung Gun SHIM

IPC分类号： G21C9/02

CPC分类号： G21C9/02 ,  G21C15/182 ,  G21D1/02 ,  G21D3/06 ,  G21D7/04 ,  Y02E30/40

摘要： An apparatus for charging an emergency battery, which provides an emergency power to an emergency core cooling apparatus including an electric pump or a steam pump includes a thermoelectric generation device configured to detect a decay heat and a residual heat produced in a nuclear power plant and configured to convert the detected heat to an electric energy; an electric energy conversion unit connected to the thermoelectric generation device to output a current generated in the thermoelectric generation device as a constant voltage; and the emergency battery configured to store a power outputted from the electric energy conversion unit.

摘要翻译： 一种对包括电动泵或蒸汽泵的应急芯冷却装置提供应急电力的紧急电池充电装置包括：热电发电装置，其被配置为检测核电厂产生的衰变热量和余热， 将检测到的热量转换成电能; 连接到所述热电发生装置的电能转换单元，其将在所述热电发电装置中产生的电流输出为恒定电压; 所述应急电池被配置为存储从所述电能转换单元输出的电力。

公开(公告)号：US20100316177A1

公开(公告)日：2010-12-16

申请号：US12722662

申请日：2010-03-12

申请人： Kevin J. Stambaugh ,  Paul K. DeSantis ,  Allan R. Mackovjak ,  John P. McLaughlin

发明人： Kevin J. Stambaugh ,  Paul K. DeSantis ,  Allan R. Mackovjak ,  John P. McLaughlin

IPC分类号： G21C7/06

CPC分类号： G21C7/117 ,  G21C7/14 ,  G21C9/02 ,  Y02E30/39

摘要： A control rod drive mechanism (CRDM) for use in a nuclear reactor, the CRDM comprising: a connecting rod connected with at least one control rod; a lead screw; a drive mechanism configured to linearly translate the lead screw; an electromagnet coil assembly; and a latching assembly that latches the connecting rod to the lead screw responsive to energizing the electromagnet coil assembly and unlatches the connecting rod from the lead screw responsive to deenergizing the electromagnet coil assembly. The latching assembly is secured with and linearly translates with the lead screw, while the electromagnet coil assembly does not move with the lead screw. The electromagnet coil assembly is at least coextensive with a linear translation stroke over which the drive mechanism is configured to linearly translate the lead screw.

摘要翻译： 一种用于核反应堆的控制棒驱动机构（CRDM），所述CRDM包括：与至少一个控制棒连接的连杆; 导螺杆 驱动机构，其构造成线性地平移所述丝杠; 电磁线圈组件; 以及闩锁组件，其响应于激励所述电磁线圈组件而将所述连接杆锁定到所述导螺杆，并且响应于对所述电磁线圈组件断电而使所述连杆从所述导螺杆解锁。 闩锁组件与导螺杆固定并直线平移，而电磁线圈组件不会随着导螺杆移动。 电磁线圈组件至少与线性平移行程共同延伸，驱动机构在该平移行程上构造成线性平移导螺杆。

公开(公告)号：US20040196945A1

公开(公告)日：2004-10-07

申请号：US10480466

申请日：2003-12-12

发明人： Gerard Barbe ,  Alain Blocquel ,  Dominique Hertz ,  Gilles Morel

IPC分类号： G21C007/06

CPC分类号： G21C17/017 ,  G21C7/08 ,  G21C9/02 ,  Y02E30/39

摘要： After a nuclear reactor has been stopped and allowed to cool down following a period of operation, action is taken in a pool of the nuclear reactor on at least one guide tube of the activated upper internal equipment of the nuclear reactor to enlarge (21b, 21c) guide channels (16b, 16c) of the guide tube (8) in at least one continuous guidance zone. The enlargement is preferably performed by machining discontinuous cavities along the length of the guide channel (16b, 16c). Enlargement is preferably performed on the guide tube (8) in place within the upper internal equipment that has been placed on a storage stand in the reactor pool.

摘要翻译： 在一个核反应堆已经停止并允许在一段时间后冷却下来，在核反应堆的活化的上部内部设备的至少一个导管上的核反应堆池中采取行动来扩大（21b，21c ）引导通道（16b，16c）在至少一个连续引导区域中。 优选地，通过沿引导通道（16b，16c）的长度加工不连续空腔来进行放大。 优选地，在已经放置在反应池中的储存架上的上部内部设备中的引导管（8）上进行放大。

公开(公告)号：US5059386A

公开(公告)日：1991-10-22

申请号：US508640

申请日：1990-04-13

申请人： Giovanni E. Farello ,  Antonio Naviglio

发明人： Giovanni E. Farello ,  Antonio Naviglio

IPC分类号： G21C9/02

CPC分类号： G21C9/02 ,  Y02E30/40

摘要： A mechanism for automatically releasing the control bars in a nuclear reactor following an increase of the temperature in the nuclear boiler includes a thermal sensor suitable for producing a mechanical force or a torque as a function of the temperature and such as to operate a mechanical actuator which provides to unlock the device that holds said control bars causing in this way their fall under the force of gravity.

公开(公告)号：US4986952A

公开(公告)日：1991-01-22

申请号：US302279

申请日：1989-01-27

申请人： Jean-Michel Bourin ,  Jean-Lucien Mourlevat ,  Gilbert Sengler

发明人： Jean-Michel Bourin ,  Jean-Lucien Mourlevat ,  Gilbert Sengler

IPC分类号： G21C7/36 ,  G21C9/02 ,  G21C17/00 ,  G21D3/04 ,  G21D3/06

CPC分类号： G21C7/36 ,  G21C9/02 ,  G21D3/04 ,  Y02E30/39

摘要： Protection against the consequences of a cluster of control rods falling accidentally is provided by four chains, each of which includes two neutron flux detectors (D1A, D1B), two primary treatment circuits (R1A, S1A and R1B, S1B) associated with said two detectors such that each provides a primary fall signal in the event of the flux measured by the corresponding detector decreasing rapidly, and an OR gate (P1) for providing an output fall signal from the chain in the event of at least one of said primary signals being present. The detectors (D1A, D4B, D3A, D1B, D2A, D3B, D4A and D2B) are angularly distributed around the vertical axis (A) of the core (2). A secondary treatment circuit (6) causes an emergency reactor stop to take place in the event that it receives fall signals at the outputs from at least two chains.

摘要翻译： 防止一组控制棒意外掉落的后果的保护由四个链提供，每个链包括两个中子通量检测器（D1A，D1B），与所述两个检测器相关联的两个主处理电路（R1A，S1A和R1B，S1B） 使得在由对应的检测器测量的通量快速下降的情况下，每个提供初级跌倒信号;以及用于在所述主信号中的至少一个的情况下提供来自所述链的输出下降信号的“或”门（P1） 当下。 检测器（D1A，D4B，D3A，D1B，D2A，D3B，D4A和D2B）围绕铁芯（2）的垂直轴线（A）成角度地分布。 在二级处理电路（6）在至少两条链的输出处接收到跌落信号的情况下，使紧急电抗器停止发生。

公开(公告)号：US4948551A

公开(公告)日：1990-08-14

申请号：US235598

申请日：1988-08-24

申请人： Olivier Onfroy

发明人： Olivier Onfroy

IPC分类号： G21C15/18 ,  G21C9/02 ,  G21D3/04 ,  G21D3/06

CPC分类号： G21D3/06 ,  G21C9/02 ,  Y02E30/32

摘要： In the event of an incident in the secondary cooling circuit of a nuclear reactor preventing cooling the water in the primary circuit of the steam generators (2) which are common to both circuits, an emergency stop instruction is issued in order to cause control and stop rods to fall into the core of the reactor. If this instruction is not executed, and if the reactor remains at a high power level, an instruction is issued to stop the primary pumps. A rapid increase in the temperature of the water in the core then slows down the nuclear reaction soon enough to prevent subsequent excess pressure from damaging the primary circuit. The invention is particularly applicable to electricity-generating nuclear power stations.

摘要翻译： 在核反应堆的二次冷却回路发生事故的情况下，防止对两个电路共同的蒸汽发生器（2）的一次回路中的水进行冷却，发出紧急停止指令，以便控制和停止 棒落入反应堆的核心。 如果不执行该指令，并且如果电抗器保持在高功率电平，则发出指令来停止主泵。 芯中的水的温度迅速增加，然后使核反应减慢，足以防止随后的过量压力损坏初级回路。 本发明特别适用于发电核电站。

公开(公告)号：US4851183A

公开(公告)日：1989-07-25

申请号：US194772

申请日：1988-05-17

申请人： Viktor E. Hampel

发明人： Viktor E. Hampel

IPC分类号： G21C7/26 ,  G21C7/28 ,  G21C9/02 ,  G21C11/06 ,  G21C13/00 ,  G21C15/257

CPC分类号： G21D1/00 ,  F28D15/00 ,  F28D15/0275 ,  F28D15/06 ,  G21C11/06 ,  G21C13/00 ,  G21C15/257 ,  G21C7/26 ,  G21C7/28 ,  G21C9/02 ,  F28D2021/0054 ,  Y02E30/39 ,  Y10S376/911

摘要： A nuclear reactor for generating electricity is disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working flud in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast-acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor.

摘要翻译： 用于发电的核反应堆位于可以使用常规钻井技术钻孔的垂直孔的底部的地下。 反应堆堆芯的主要冷却剂是位于孔底部的热源和靠近地球表面的热交换装置之间的孔中的多个热力学耦合的热管中的工作流体。 此外，主冷却剂（由反应堆堆芯中的热管中的工作流体组成）可缓和中子并调节其反应性，从而保持反应堆的功率基本恒定。 在其使用寿命结束时，反应堆堆芯可能被放弃到位。 在发生事故或放弃的情况下，大气中的隔离是通过沿着孔放置的爆炸封闭物和机械阀的操作提供的。 本发明结合了针对小型，高效率，基于空间的核电站开发和测试的技术，开发并用于核武器地下试验的快速闭合机制技术。 本发明提供了一种核能装置，它是从最可能想到的反应堆事故中安全的，即核动力堆反应堆地面附近的核武器爆炸。