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公开(公告)号：US4562038A
公开(公告)日：1985-12-31
申请号：US441872
申请日：1982-11-15
Applicant: Raphael Assedo , Eric Dubreux
Inventor： Raphael Assedo , Eric Dubreux
CPC classification number: G21C7/08 , G21C7/117 , G21Y2002/101 , G21Y2004/30 , G21Y2004/302 , Y02E30/39
Abstract: A device for guiding a control cluster consisting of several absorbing rods consisting of a casing in which are mounted continuous-guiding sleeves each provided with at least one cylindrical slide suitable for the vertical guiding of a rod, and each open with a vertical slot emerging in the slide. Each guiding slide (631, 641) is associated with two orifices (635, 645) forming a hollow in the two lips (633, 643) of the slot (632, 642) so that, when a rod (31) is in contact with the lips, the interior of the slide communicates with the slot.
Abstract translation: 一种用于引导由几个由一个壳体组成的吸收杆组成的控制组件的装置，其中安装有连续导向套筒，每个连续导向套筒设置有至少一个适用于杆的垂直导向的圆柱形滑动件，并且每个都带有垂直狭槽， 幻灯片。 每个引导滑块（631,661）与在槽（632,642）的两个唇缘（633,643）中形成中空的两个孔（635,645）相关联，使得当杆（31）接触时 与嘴唇，滑块的内部与插槽通信。
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公开(公告)号：US4481164A
公开(公告)日：1984-11-06
申请号：US358962
申请日：1982-03-17
Applicant: Lawrence R. Bollinger
Inventor： Lawrence R. Bollinger
CPC classification number: G21C7/103 , G21C7/12 , G21C7/14 , G21Y2002/201 , G21Y2002/304 , G21Y2004/30 , Y02E30/39
Abstract: Reactivity control assembly for nuclear reactor comprises supports stacked above reactor core for holding control rods. Couplers associated with the supports and a vertically movable drive shaft have lugs at their lower ends for engagement with the supports.
Abstract translation: 用于核反应堆的反应性控制组件包括堆叠在反应堆堆芯上方的用于保持控制棒的支撑件。 与支撑件相关联的联接器和可垂直移动的驱动轴在其下端具有用于与支撑件接合的凸耳。
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公开(公告)号：US4476086A
公开(公告)日：1984-10-09
申请号：US374237
申请日：1982-05-03
Applicant: Klaus Kerz
Inventor： Klaus Kerz
CPC classification number: G21C7/12 , G21Y2002/30 , G21Y2004/301 , G21Y2004/304 , Y02E30/39 , Y10S294/906
Abstract: Coupler for absorber rods being suspended during operation of nuclear reactors including a plurality of actuating elements being movable for individually and jointly releasing the coupler, the movement of each of the actuating elements for releasing the coupler being independently controllable.
Abstract translation: 用于在核反应堆运行期间暂停吸收杆的耦合器，包括多个致动元件，其可移动以单独地和共同地释放耦合器，用于释放耦合器的每个致动元件的移动是可独立控制的。
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公开(公告)号：US4204909A
公开(公告)日：1980-05-27
申请号：US805251
申请日：1977-06-10
Applicant: Nicholas Giuggio , Richard C. Noyes , Shakir U. Zaman
Inventor： Nicholas Giuggio , Richard C. Noyes , Shakir U. Zaman
Abstract: A self-actuated mechanism within a safety assembly in a liquid metal nuclear reactor comprising sensor fuel pins located in a reactor coolant flow path, a sensor bulb containing NaK located near the upper end of the sensor fuel pins and in the reactor coolant flow path, and a sensor tube connecting the sensor bulb to a metal bellows and push rod. The motion of the push rod resulting from the temperature dependent change in the NaK volume actuates a safety rod release mechanism when a predetermined coolant temperature is reached.
Abstract translation: 液体金属核反应堆中的安全组件内的自致动机构，包括位于反应堆冷却剂流动路径中的传感器燃料销，包含位于传感器燃料销的上端附近和反应堆冷却剂流动路径中的NaK的传感器灯泡， 以及将传感器灯泡连接到金属波纹管和推杆的传感器管。 当达到预定的冷却剂温度时，由NaK体积的温度依赖性变化导致的推杆的运动致动安全杆释放机构。
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公开(公告)号：US4138320A
公开(公告)日：1979-02-06
申请号：US920416
申请日：1978-06-29
Applicant: Alan L. Grantz
Inventor： Alan L. Grantz
CPC classification number: G21C7/36 , G21C7/16 , G21C9/027 , G21Y2002/205 , G21Y2002/50 , G21Y2004/302 , G21Y2004/401 , Y02E30/39
Abstract: A fluidic self-actuating control assembly for use in a reactor wherein no external control inputs are required to actuate (scram) the system. The assembly is constructed to scram upon sensing either a sudden depressurization of reactor inlet flow or a sudden increase in core neutron flux. A fluidic control system senses abnormal flow or neutron flux transients and actuates the system, whereupon assembly coolant flow reverses, forcing absorber balls into the reactor core region.
Abstract translation: 一种在反应器中使用的流体自致动控制组件，其中不需要外部控制输入来驱动（阻塞）系统。 该组件被构造成在感测到反应器入口流的突然减压或者核心中子通量的突然增加时被冲击。 流体控制系统感测异常流量或中子通量瞬变并致动系统，于是组装冷却剂流反向，迫使吸收器球进入反应堆堆芯区域。
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Patent Agency Ranking
公开(公告)号：US4110157A
公开(公告)日：1978-08-29
申请号：US740637
申请日：1976-11-10
Applicant: Felix S. Jabsen
Inventor： Felix S. Jabsen
CPC classification number: G21C7/12 , G21Y2002/206 , G21Y2002/402 , G21Y2004/30 , G21Y2004/301 , Y02E30/39 , Y10T403/583 , Y10T403/7007
Abstract: An illustrative embodiment of the invention provides a control rod system locking device adapted to engage an elongated extension shaft, releasably coupled at one end to the control rod assembly and releasably coupled at its other end to the control rod drive, to prevent rotation of the shaft about its longitudinal axis with respect to the control rod assembly.
Abstract translation: 本发明的说明性实施例提供了一种控制杆系统锁定装置，其适于接合细长的延伸轴，该细长的延伸轴在一端可释放地联接到控制杆组件并且在其另一端可释放地联接到控制杆驱动器，以防止轴的旋转 围绕其纵向轴线相对于控制杆组件。
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公开(公告)号：US4082610A
公开(公告)日：1978-04-04
申请号：US578437
申请日：1975-05-16
Applicant: John C. Matthews
Inventor： John C. Matthews
CPC classification number: G21C7/14 , G21C7/20 , G21Y2002/206 , G21Y2004/30 , Y02E30/39
Abstract: A snubber cartridge assembly is mounted to the nozzle of a control rod drive mechanism to insure that the snubber assembly will be located within the liquid filled section of a nuclear reactor vessel whenever the control rod drive is assembled thereto. The snubber assembly includes a piston mounted proximate to the control rod connecting end of the control rod drive leadscrew to allow the piston to travel within the liquid filled snubber cartridge and controllably exhaust liquid therefrom during a "scram" condition. The snubber cartridge provides three separate areas of increasing resistance to piston travel to insure a speedy but safe "scram" of the control rod into the reactor.
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公开(公告)号：US4075059A
公开(公告)日：1978-02-21
申请号：US681101
申请日：1976-04-28
Applicant: Stephen James Bruno , Stephen Alfred Dunn , Marvin Raber
Inventor： Stephen James Bruno , Stephen Alfred Dunn , Marvin Raber
CPC classification number: G21C7/00 , G21D3/04 , G21Y2002/202 , G21Y2002/207 , G21Y2004/40 , Y02E30/39
Abstract: A method of operating a nuclear power reactor is disclosed which enables an accelerated power reduction of the reactor without completely shutting the reactor down. The method includes monitoring the incidents which, upon their occurrence, would require an accelerated power reduction in order to maintain the reactor in a safe operation mode; calculating the power reduction required on the occurrence of such an incident; determining a control rod insertion sequence for the normal operation of the reactor, said sequence being chosen to optimize reactor power capability; selecting the number of control rods necessary to respond to the accelerated power reduction demand, said selection being made according to a priority determined by said control rod insertion sequence; and inserting said selected control rods into the reactor core.
Abstract translation: 公开了一种操作核电反应堆的方法，其能够在不完全关闭反应堆的情况下加速反应堆的功率降低。 该方法包括监测事故发生时，需要加速减少功率以维持反应堆处于安全运行模式; 计算发生此类事件所需的功率降低; 确定用于反应堆的正常操作的控制棒插入顺序，选择所述序列以优化反应堆功率能力; 选择响应于加速功率降低需求所需的控制棒的数量，所述选择根据由所述控制棒插入顺序确定的优先级进行; 并将所述选定的控制棒插入反应堆堆芯。
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公开(公告)号：US4045283A
公开(公告)日：1977-08-30
申请号：US537283
申请日：1974-12-30
Applicant: Richard Croissant Noyes , Clive Frederick George Dupen , Donald Martin Barrus , Edward Arnold Siegel
Inventor： Richard Croissant Noyes , Clive Frederick George Dupen , Donald Martin Barrus , Edward Arnold Siegel
CPC classification number: G21C7/12 , G21C13/073 , G21C17/02 , G21C17/10 , G21C19/00 , G21Y2002/401 , G21Y2002/50 , G21Y2004/305 , G21Y2004/501 , G21Y2004/504 , Y02E30/39
Abstract: An improved core servicing apparatus for a nuclear reactor having a vessel, a head for the vessel, one or more penetration openings in the head and a core within the vessel of the type having an array of fuel assemblies and including apertures in the array for neutron absorbers. The servicing apparatus includes a support column adapted to be supported by and depend from the head in registry with a penetration opening; a plurality of core servicing elements which may include neutron absorber actuating means and/or instrument packages are supported by the support column; and means are provided for laterally displacing at least some of the servicing elements relative to the support column between a laterally compact and a laterally expanded configuration.In one embodiment, instruments may be located at the lower end of long resilient cables and are longitudinally movable within and beyond guide channels supported by the support column. The guide channels are directed outward at their lower ends to direct a descending instrument and cable outwardly.
Abstract translation: 一种用于核反应堆的改进的核心维修装置，其具有容器，用于容器的头部，头部中的一个或多个穿透开口和容器内的芯，其具有燃料组件阵列并且包括用于中子的阵列中的孔 吸收体。 维修设备包括支撑柱，其适于由头部支撑并依靠头部与登记孔对准; 可以包括中子吸收器致动装置和/或器械包的多个核心维修元件由支撑柱支撑; 并且提供了用于在侧向紧凑和横向膨胀构型之间相对于支撑柱侧向移位至少一些维修元件的装置。
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40.发明授权Gripping device, especially for use in manipulating control bars in a nuclear reactor 失效夹紧装置，特别用于操纵核反应堆中的控制杆
公开(公告)号：US4030973A
公开(公告)日：1977-06-21
申请号：US485264
申请日：1974-07-02
Applicant: Bernhard Hoffmeister , Gerhard Dose
Inventor： Bernhard Hoffmeister , Gerhard Dose
CPC classification number: G21C19/10
Abstract: A device for gripping bundles of control bars or rods for extracting the control bars from and introducing the control bars into fuel cells of nuclear reactors in which the control bars are in bundles connected by a spider-like head at the top and the gripping device includes a plate with a perforation through which the head can pass. When the head is released from the fuel cell and lifted upwardly through the plate, the plate provides lateral guidance for the control rods thereby facilitating replacement of the control rods into a fuel cell. The gripping device includes a reciprocable gripper body in a gripper tool detachably connectable thereto and to said head and guided on said plate by guide members projecting from the plate.
Abstract translation: 一种用于夹紧控制杆或杆的装置，用于将控制杆从控制杆抽出并将其引入到核反应堆的燃料电池中，其中控制棒通过顶部的蜘蛛状头连接在一起并且夹持装置包括 具有头部穿过的穿孔板。 当头部从燃料电池释放并且向上提升穿过板时，该板为控制杆提供侧向引导，从而便于将控制杆更换为燃料电池。 夹持装置包括可拆卸地连接到其上的夹持器工具中的可往复运动的夹持器主体，并且通过从板突出的引导构件在所述板上引导。
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