Gripper assembly for inserting and removing burnable absorber rods and
thimble plugs in a nuclear reactor fuel assembly
    11.
    发明授权
    Gripper assembly for inserting and removing burnable absorber rods and thimble plugs in a nuclear reactor fuel assembly 失效
    用于在核反应堆燃料组件中插入和移除可燃吸收棒和套筒塞的夹具组件

    公开(公告)号:US4772446A

    公开(公告)日:1988-09-20

    申请号:US932244

    申请日:1986-11-19

    摘要: Apparatus for releasably engaging an elongated member that is releasably connected to the top nozzle of a nuclear reactor fuel assembly. The top nozzle has an adapter plate disposed at its lower end having at least one passageway therethrough through which the elongated member is disposed. The elongated member has a releasable latching structure at one end that is able to be engaged by the apparatus, having at least one latching member movable between a latched position in which the latching member is able to engage said adapter plate and secure the absorber rod in a stationary relationship with respect to the adapter plate and an unlatched position in which the latching member is able to disengage from said adapter plate so that the elongated member be removed from the fuel assembly. The apparatus comprises a hollow releasing member for moving the latching member of the latching structure between its latched position and its unlatched position, an engaging member connected to the releasing member and extending downwardly through the hollow portion of the releasing member, and an actuating member extending downwardly through the hollow portion of the releasing member and coacting with the engaging member to releasably engage the latching structure.

    摘要翻译: 用于可释放地接合可释放地连接到核反应堆燃料组件的顶部喷嘴的细长构件的装置。 顶部喷嘴具有设置在其下端的适配器板,其具有穿过其中的至少一个通道,细长构件通过该通道布置。 细长构件在一端具有可释放的闩锁结构,其能够被该装置接合,具有至少一个闩锁构件,该锁定构件可在闩锁位置之间移动,在闩锁位置中闩锁构件能够接合所述适配器板并将吸收杆固定在 相对于适配器板的固定关系和解锁位置,其中闩锁构件能够与所述适配器板脱离,使得细长构件从燃料组件移除。 该装置包括中空释放构件,用于将闩锁构件的闩锁构件在其闩锁位置和其解锁位置之间移动;接合构件,其连接到释放构件并向下延伸穿过释放构件的中空部分;以及致动构件, 向下穿过释放构件的中空部分并与接合构件共同作用以可释放地接合闩锁结构。

    Refueling of nuclear reactors
    12.
    发明授权
    Refueling of nuclear reactors 失效
    加油核反应堆

    公开(公告)号:US4666658A

    公开(公告)日:1987-05-19

    申请号:US552231

    申请日:1983-11-16

    CPC分类号: G21C19/10 Y10S294/906

    摘要: During unrodded refueling, the drive rods and the control rods and coolant-displacement rods, attached to the drive rods, are removed from a fuel assembly, preliminary to the transfer of the fuel assembly, and are reinserted in the reactor after a replacement fuel assembly has been positioned in the reactor. Prior to the transfer of a fuel assembly, a lifting rig is secured to the upper-internals support. A lift plate is removeably mounted on latches in a lower position of the lifting rig. The latches are released and the lift plate is connected to the drive rods. The lift plate is then raised and removeably mounted on latches in an upper position on the lifting rig. In this position, the control rods and coolant-displacement rods are in the guides in the upper internals of the reactor. During the lift-plate raising operation, the loading on the drive rods is monitored and if the loading exceeds a predetermined magnitude, the excess loading is indicated. After the lift plate and the rods suspended from it are positioned on the latches in the upper position, the lifting rig and the upper internals and rods attached to the lift plate are removed from the reactor so that the unrodded transfer of the fuel assemblies may proceed. The replacement of the rods proceeds reversely. In this case, the device which indicates excess loading of a drive rod operates to indicate that the control rod or coolant-displacement rod connected to the drive rod has encountered an obstruction.

    摘要翻译: 在未加油的加油过程中,连接到驱动杆上的驱动杆和控制棒以及冷却剂置换杆从燃料组件中移除,预先用于燃料组件的传送,并且在更换燃料组件之后重新插入反应器 已经定位在反应堆中。 在燃料组件的传送之前,提升装置被固定到上部内部支撑件上。 提升板可拆卸地安装在提升装置的较低位置的闩锁上。 闩锁被释放,升降板连接到驱动杆上。 然后升降板升高并可拆卸地安装在升降装置的上部位置的闩锁上。 在这个位置上,控制棒和冷却剂置换杆位于反应器的上部内部的引导件中。 在提升板提升操作期间,监控驱动杆上的负载,并且如果负载超过预定量值,则指示超负荷。 在升降板和悬挂在其上的杆被定位在上部位置的闩锁上之后,提升装置以及附接到提升板的上部内件和杆被从反应器中移出,使得燃料组件的无序转移可以进行 。 棒的更换反向进行。 在这种情况下,指示驱动杆的过度加载的装置操作以指示连接到驱动杆的控制棒或冷却剂 - 移动杆遇到障碍物。

    Apparatus for dismantling and disposing of fuel assemblies
    13.
    发明授权
    Apparatus for dismantling and disposing of fuel assemblies 失效
    用于拆卸和处理燃料组件的装置

    公开(公告)号:US4511499A

    公开(公告)日:1985-04-16

    申请号:US359552

    申请日:1982-03-18

    摘要: Method and apparatus for dismantling, shearing and compacting a fuel assembly frame skeleton. A frame is provided which can be placed into the transfer canal of a fuel-handling building for severing a bottom nozzle from the thimble tubes and grids of the frame skeleton, compacting the remainder of the skeleton, and then further severing the thimble tubes and grids into shorter longitudinal lengths, and placing the shortened compacted severed pieces into a container for off-site shipment or on-site storage.

    摘要翻译: 用于拆卸,剪切和压实燃料组件框架骨架的方法和装置。 提供了一个框架,可以将其放置在燃料处理建筑物的输送管道中,用于从底架喷嘴与框架骨架的顶管和网格分离底部喷嘴,压实骨架的其余部分,然后进一步切断套管和网格 变短的纵向长度,并将缩短的压实切割件放置在用于非现场装运或现场存储的容器中。

    Permanent seal ring for a nuclear reactor cavity
    14.
    发明授权
    Permanent seal ring for a nuclear reactor cavity 失效
    用于核反应堆腔的永久密封环

    公开(公告)号:US4170517A

    公开(公告)日:1979-10-09

    申请号:US502315

    申请日:1974-09-03

    CPC分类号: G21C13/028 Y02E30/40

    摘要: A nuclear reactor containment arrangement incorporating a permanent cavity to vessel seal in the form of a flexible quarter-circular annular steel gasket affixed to and extending between the reactor vessel seal plate and cavity wall. The seal functions to isolate the periphery of the vessel from a permanent water-tight compartment above the reactor vessel which is flooded during refueling operations to minimize the release of radiation upon exposure of the nuclear core. The seal is designed to accommodate both radial and axial expansion of the pressure vessel relative to the cavity wall occurring during reactor operation without breaking the water-tight integrity of the seal. The pressure vessel ventilation system is provided with an air exit duct at the reactor nozzle level to facilitate the circulation of air around the periphery of the vessel which would otherwise be restricted at the seal to vessel interface.

    摘要翻译: 一种核反应堆安全壳装置,其包括固定到反应堆容器密封板和空腔壁之间并在反应堆容器密封板和空腔壁之间延伸的柔性四分之一圆形环形钢垫片形式的容器密封件的永久空腔。 密封件用于将容器的周边与加油操作期间淹没的反应堆容器上方的永久性不透水隔室隔离,以使核芯暴露时辐射的释放最小化。 密封件被设计成适应压力容器相对于反应器操作期间发生的空腔壁的径向和轴向膨胀,而不破坏密封件的水密完整性。 压力容器通风系统在反应器喷嘴水平处设置有空气出口管道,以便于围绕容器外围的空气循环,否则这些空气将被限制在密封件处于容器界面处。

    Lower reactor internals up-ending device
    15.
    发明授权
    Lower reactor internals up-ending device 有权
    下反应器内件最终装置

    公开(公告)号:US06266386B1

    公开(公告)日:2001-07-24

    申请号:US09417350

    申请日:1999-10-13

    IPC分类号: G21C1902

    CPC分类号: G21C19/02 G21C19/207

    摘要: An apparatus and method are provided for inverting the lower internal assembly of a nuclear reactor. The apparatus includes a frame which is sized to receive the lower internal assembly. The frame supports the lower internal assembly as it is being inverted. The apparatus also includes a spider assembly which fits within the lower internal assembly and provides support for a baffle assembly located therein. The method includes the steps of removing the lower internal assembly from a reactor vessel and rotating the lower internal assembly prior to performing maintenance.

    摘要翻译: 提供了一种用于反转核反应堆的下部内部组件的装置和方法。 该装置包括尺寸适于接收下部内部组件的框架。 框架支撑下部内部组件,因为它被倒置。 该装置还包括一个安装在下部内部组件内的一个蜘蛛组件,并为位于其中的挡板组件提供支撑。 该方法包括以下步骤:从反应堆容器移除下部内部组件,并在执行维护之前旋转下部内部组件。

    Method for limiting movement of a thermal shield for a nuclear reactor,
and thermal shield displacement limiter therefor
    17.
    发明授权
    Method for limiting movement of a thermal shield for a nuclear reactor, and thermal shield displacement limiter therefor 失效
    用于限制用于核反应堆的热屏蔽件的运动的方法,以及用于其的热屏蔽位移限制器

    公开(公告)号:US4849158A

    公开(公告)日:1989-07-18

    申请号:US152530

    申请日:1988-02-05

    IPC分类号: G21C11/08

    CPC分类号: G21C11/08 Y02E30/40

    摘要: A method for limiting movement of a thermal shield of a nuclear reactor, and a thermal shield displacement limiter therefor, is provided where at least four and preferably six or more key-way inserts are positioned in pockets machined in the upper portion of a thermal shield, and bolted and doweled to the thermal shield. Each key-way insert is engaged by a limiter key that is bolted and doweled to the core barrel to tangentially restrain movement of the thermal shield relative to the core barrel, while allowing radial and axial movement to the thermal shield relative to the core barrel. Preferably, lock pins extend diametrically through the bolts and dial pins and engage the key-way insert and limiter key, respectively, to lock the bolts and dowels in position, and the engaging surfaces between the key-way inserts and the limiter keys are wear hardened.

    Thimble grip fuel assembly handling tool
    18.
    发明授权
    Thimble grip fuel assembly handling tool 失效
    套管夹紧燃油组件处理工具

    公开(公告)号:US4834934A

    公开(公告)日:1989-05-30

    申请号:US152285

    申请日:1988-02-04

    IPC分类号: G21C19/19 G21C19/105

    CPC分类号: G21C19/105 Y10S294/906

    摘要: A thimble grip fuel assembly handling tool (20) for transporting fully loaded fuel assemblies (52) is disclosed. The tool (20) comprises an elongated mast (23) slidingly disposed within an elongated cylinder (113), the cylinder being of a length less than the mast (23) such that the tool defines a mast fill-up position (126) and a mast full-down position (128). A cage (110) assembly acts to protect the gripping means (32) when the tool is transported in the mast full-up position (126). The gripping means (32) is comprised of a plurality of gripping members (49) which grip the inside diameter of control rod guide thimbles (50). The load path is distributed in the tool such that when the fuel assembly (52) secured to the gripping means (32) is raised, the weight of the fully loaded fuel assembly (52) acts to increase the gripping force on the fuel assembly. A number of indicators on the tool act to indicate to an operator: when the tool is in the mast full-down position; when the gripping members (49) have been fully actuated; and if there is any slipping of the gripping members within the fuel assemblies. The tool also includes a secondary gripping mechanism which engages the top nozzle of the fuel assembly.

    Apparatus for vertically tubing a heat exchanger
    19.
    发明授权
    Apparatus for vertically tubing a heat exchanger 失效
    用于竖直管道换热器的装置

    公开(公告)号:US4319725A

    公开(公告)日:1982-03-16

    申请号:US132567

    申请日:1980-03-21

    IPC分类号: F16L3/223 F28F9/013 F16L3/22

    摘要: A support framework for a double column of U-shaped tubes of a heat exchanger for vertically suspending the tubes above the heat exchanger during a tubing operation is shown. That portion of the framework which supports the U-bends of the tubes is primarily used to support the tubes above the tubesheet and lower the tubes into the tubesheet as a unit. The U-bend support framework includes a vertical member in which the separate tubes of the double column are clamped to normally prevent movement of the tubes therein and also permits individual release of the tubes when necessary.

    摘要翻译: 示出了用于在管道操作期间将管垂直悬挂在热交换器上方的热交换器的双列U形管的支撑框架。 支撑管的U形弯曲的框架的该部分主要用于支撑管板上方的管,并将管子作为一个单元将管子下降。 U形弯曲支撑框架包括垂直构件,其中双柱的单独的管被夹紧,以正常地防止管中的管的移动,并且还可以在必要时单独释放管。

    Radiation shielded movable work station apparatus
    20.
    发明授权
    Radiation shielded movable work station apparatus 失效
    辐射屏蔽可移动工作站设备

    公开(公告)号:US4200172A

    公开(公告)日:1980-04-29

    申请号:US896531

    申请日:1978-04-14

    摘要: Described is a movable work station apparatus including travelling-hoist supported tools and a vertically and rotarywise movable frame-carried radiation-shielded enclosure, or gondola, for working personnel involved in tube-bundle-replacement tasks performed within the shell of a steam generator in a nuclear plant. The enclosure, or gondola, is divided and accommodates four upright workers in mutually-facing pairs at opposite sides of a work-accommodating clearanceway observable and accessible from the gondola interior via lead glass windows and hand holes.

    摘要翻译: 描述了一种可移动工作站设备,其包括行进式起重机支撑的工具和用于在蒸汽发生器的壳体内执行的管束更换任务的工作人员的垂直和可旋转移动的框架式辐射屏蔽外壳或吊舱 一个核电厂。 外壳或吊舱分开,并容纳四个直立工人,在相互面对的对中,可以从吊舱内部通过铅玻璃窗和手孔观察到并接近。