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    PRESSURE VESSEL SLIDING SUPPORT UNIT AND SYSTEM USING THE SLIDING SUPPORT UNIT
    1.
    发明申请
    PRESSURE VESSEL SLIDING SUPPORT UNIT AND SYSTEM USING THE SLIDING SUPPORT UNIT 失效
    压力容器滑动支撑单元和使用滑动支撑单元的系统

    公开(公告)号：US20110038450A1

    公开(公告)日：2011-02-17

    申请号：US12541493

    申请日：2009-08-14

    申请人： Michael R. Breach ,  David J. Keck ,  Gerald A. Deaver

    发明人： Michael R. Breach ,  David J. Keck ,  Gerald A. Deaver

    IPC分类号： G21C13/024 ,  B65D25/24

    CPC分类号： G21C13/024 ,  F16J12/00 ,  G21C13/04 ,  Y02E30/40 ,  Y10T137/7039

    摘要： Provided is a sliding support and a system using the sliding support unit. The sliding support unit may include a fulcrum capture configured to attach to a support flange, a fulcrum support configured to attach to the fulcrum capture, and a baseplate block configured to support the fulcrum support. The system using the sliding support unit may include a pressure vessel, a pedestal bracket, and a plurality of sliding support units.

    摘要翻译： 提供了一种滑动支撑件和使用滑动支撑单元的系统。 滑动支撑单元可以包括构造成附接到支撑凸缘的支点捕获，构造成附接到支点捕获的支点支撑件和被配置为支撑支点支撑件的基板块。 使用滑动支撑单元的系统可以包括压力容器，基座支架和多个滑动支撑单元。

    REACTOR PRESSURE VESSEL HEAD VENTS AND METHODS OF USING THE SAME
    3.
    发明申请
    REACTOR PRESSURE VESSEL HEAD VENTS AND METHODS OF USING THE SAME 有权
    反应器压力容器头部及其使用方法

    公开(公告)号：US20120177164A1

    公开(公告)日：2012-07-12

    申请号：US12985620

    申请日：2011-01-06

    申请人： John L. Gels ,  David J. Keck ,  Gerald A. Deaver

    发明人： John L. Gels ,  David J. Keck ,  Gerald A. Deaver

    IPC分类号： G21C13/073

    CPC分类号： G21C13/022 ,  G21C9/004 ,  Y02E30/40

    摘要： Internal head vents are usable in nuclear reactors and include piping inside of the reactor pressure vessel with a vent in the reactor upper head. Piping extends downward from the upper head and passes outside of the reactor to permit the gas to escape or be forcibly vented outside of the reactor without external piping on the upper head. The piping may include upper and lowers section that removably mate where the upper head joins to the reactor pressure vessel. The removable mating may include a compressible bellows and corresponding funnel. The piping is fabricated of nuclear-reactor-safe materials, including carbon steel, stainless steel, and/or a Ni—Cr—Fe alloy. Methods install an internal head vent in a nuclear reactor by securing piping to an internal surface of an upper head of the nuclear reactor and/or securing piping to an internal surface of a reactor pressure vessel.

    摘要翻译： 内部通风口可用于核反应堆，并包括反应堆压力容器内的管道，反应堆上部头部有通风口。 管道从上部头部向下延伸并通过反应器外部，以允许气体逸出或被强制排出反应器外部，而不需要在上部头部上的外部管道。 管道可以包括上部和下部，其可拆卸地配合上部头部连接到反应堆压力容器的位置。 可移除的配合可以包括可压缩波纹管和相应的漏斗。 管道由核反应堆安全的材料制成，包括碳钢，不锈钢和/或Ni-Cr-Fe合金。 方法通过将管道固定到核反应堆的上部头部的内表面和/或将管道固定到反应堆压力容器的内表面来在核反应堆中安装内部头部通风口。

    Reactor pressure vessel head vents and methods of using the same
    4.
    发明授权
    Reactor pressure vessel head vents and methods of using the same 有权
    反应堆压力容器的通风口及其使用方法

    公开(公告)号：US08873695B2

    公开(公告)日：2014-10-28

    申请号：US12985620

    申请日：2011-01-06

    申请人： John L. Gels ,  David J. Keck ,  Gerald A. Deaver

    发明人： John L. Gels ,  David J. Keck ,  Gerald A. Deaver

    IPC分类号： G01S13/02 ,  G01S13/00

    CPC分类号： G21C13/022 ,  G21C9/004 ,  Y02E30/40

    摘要： Internal head vents are usable in nuclear reactors and include piping inside of the reactor pressure vessel with a vent in the reactor upper head. Piping extends downward from the upper head and passes outside of the reactor to permit the gas to escape or be forcibly vented outside of the reactor without external piping on the upper head. The piping may include upper and lowers section that removably mate where the upper head joins to the reactor pressure vessel. The removable mating may include a compressible bellows and corresponding funnel. The piping is fabricated of nuclear-reactor-safe materials, including carbon steel, stainless steel, and/or a Ni—Cr—Fe alloy. Methods install an internal head vent in a nuclear reactor by securing piping to an internal surface of an upper head of the nuclear reactor and/or securing piping to an internal surface of a reactor pressure vessel.

    摘要翻译： 内部通风口可用于核反应堆，并包括反应堆压力容器内的管道，反应堆上部头部有通风口。 管道从上部头部向下延伸并通过反应器外部，以允许气体逸出或被强制排出反应器外部，而不需要在上部头部上的外部管道。 管道可以包括上部和下部，其可拆卸地配合上部头部连接到反应堆压力容器的位置。 可移除的配合可以包括可压缩波纹管和相应的漏斗。 管道由核反应堆安全的材料制成，包括碳钢，不锈钢和/或Ni-Cr-Fe合金。 方法通过将管道固定到核反应堆的上部头部的内表面和/或将管道固定到反应堆压力容器的内表面来在核反应堆中安装内部头部通风口。

    Feedwater nozzle and method of repair
    6.
    发明授权
    Feedwater nozzle and method of repair 失效
    给水喷嘴及维修方法

    公开(公告)号：US5345484A

    公开(公告)日：1994-09-06

    申请号：US56083

    申请日：1993-05-03

    申请人： Gerald A. Deaver ,  Siamak Bourbour

    发明人： Gerald A. Deaver ,  Siamak Bourbour

    IPC分类号： G21C15/02 ,  F28F11/02 ,  G21C13/032 ,  G21C15/00

    CPC分类号： F28F11/02 ,  G21C13/032 ,  Y02E30/40

    摘要： A nozzle includes a barrel being integral with a vessel and includes a first bore. A safe end is joined at one end to the barrel by a first weld and at an opposite end to an inlet pipe at a second weld. A first thermal sleeve is disposed inside the first bore and has one end disposed in an interference fit with a second bore of the safe end. In order to repair the nozzle for reducing leakage at the interference fit between the first and second bores, a method includes removing a portion of the inlet pipe and the weld at the safe end and installing a replacement extension therefor. The extension includes a tubular body having a first fork at one end joined to the safe end by a replacement weld, and having a distal end joined to the inlet pipe at a third weld. A second fork is disposed concentrically inside the body and is integrally joined at one end with an intermediate portion of the body, and includes a distal end extending toward the safe end. A second thermal sleeve is disposed inside the first thermal sleeve and is joined at one end to the second fork and has an opposite end portion disposed in sealing cooperation with the first thermal sleeve for sealing flow therebetween to the interference fit between the first thermal sleeve and the safe end.

    摘要翻译： 喷嘴包括与容器成一体的筒，并包括第一孔。 安全端通过第一焊接在一端连接到筒体，并且在第二焊接处的入口管的相对端处连接。 第一热套筒设置在第一孔内部，并且一端设置成与安全端的第二孔过盈配合。 为了修复喷嘴以减少在第一和第二孔之间的过盈配合处的泄漏，一种方法包括在安全端移除一部分入口管和焊缝，并为此安装替换延伸部。 该延伸部包括管状体，其具有通过替换焊接在一端连接到安全端的第一叉，并且在第三焊缝处具有连接到入口管的远端。 第二叉子同心地设置在主体内部，并且在一端与主体的中间部分整体连接，并且包括朝向安全端延伸的远端。 第二热套管设置在第一热套筒的内部并且在一端连接到第二叉子并且具有与第一热套筒密封配合的相对的端部部分，用于将其间的流动密封到第一热套筒与第一热套筒之间的过盈配合 安全的结束。

    Control rod housing alignment and repair apparatus
    7.
    发明授权
    Control rod housing alignment and repair apparatus 失效
    控制杆外壳对位和修理装置

    公开(公告)号：US5059384A

    公开(公告)日：1991-10-22

    申请号：US617828

    申请日：1990-11-26

    申请人： Robert C. Dixon ,  Gerald A. Deaver ,  James R. Punches ,  Guy E. Singleton ,  John G. Erbes ,  Henry P. Offer

    发明人： Robert C. Dixon ,  Gerald A. Deaver ,  James R. Punches ,  Guy E. Singleton ,  John G. Erbes ,  Henry P. Offer

    IPC分类号： G21C7/12 ,  G21C19/02

    CPC分类号： G21C7/12 ,  G21C19/02 ,  G21C19/207 ,  G21Y2002/402 ,  G21Y2004/40 ,  G21Y2004/50 ,  G21Y2004/502 ,  Y02E30/39 ,  Y10T29/531

    摘要： In a boiling water nuclear reactor having its core, fuel support casting, and control rod guide tubes removed to expose the core plate, an apparatus and method for the submerged welding repair and replacement of the control rod drive housing at the bottom extremity of the reactor vessel is disclosed. The apparatus registers to a hole in the core plate and its corresponding guide pin. A mating fixture on the depending extremity of the shaft of the apparatus precisely fits and mates to the top of the control rod drive housing. The alignment device includes cross electronic levels sealed for submersion which levels remotely transfer through attached wiring the precise angularity between the top of the control rod drive housing on one hand and the corresponding and overlying hole in the core plate on the other hand. For the welding repair process herein, a welding cylinder apparatus fits over the depending end of the shaft of the alignment device. This welding cylinder protrudes downwardly and around the control rod drive housing mating to the stub tube through which the control rod drive housing is inserted. A rotating raceway is provided interior of the cylinder for permitting TIG welding unit to traverse around a path for weldment defined at the side of the control rod drive housing and at the top of the stub tube.

    摘要翻译： 在其核心的燃料水核反应堆，燃料支撑铸造和被拆除的控制棒导向管暴露出核心板的装置和方法，用于在反应堆的底端处的淹没焊接维修和更换控制棒驱动器壳体的装置和方法 船舶被披露。 该装置注册到芯板中的一个孔及其相应的导销上。 设备轴的固定末端上的配合夹具精确地配合并配合到控制杆驱动器壳体的顶部。 对准装置包括用于浸没密封的交叉电子水平，其水平通过附接布线远程传递一方面控制杆驱动器壳体的顶部与另一方面在芯板中的相应和上覆孔之间的精确角度。 对于这里的焊接修补过程，焊接圆柱装置装配在对准装置的轴的悬垂端上。 该焊接圆筒向下突出并且围绕控制棒驱动器壳体突出，该壳体配合到插棒管，插入管驱动器壳体。 旋转的滚道设置在气缸的内部，用于允许TIG焊接单元围绕限定在控制棒驱动器壳体侧面和短管顶部的焊接路径。

    Reactor pressure vessel assembly including a flow barrier structure
    8.
    发明授权
    Reactor pressure vessel assembly including a flow barrier structure 有权

    公开(公告)号：US10147508B2

    公开(公告)日：2018-12-04

    申请号：US14577364

    申请日：2014-12-19

    申请人： Gerald A. Deaver ,  Robin D. Sprague

    发明人： Gerald A. Deaver ,  Robin D. Sprague

    IPC分类号： G21C15/24 ,  G21C13/02 ,  G21C15/14 ,  G21C15/16 ,  G21C15/26

    摘要： A reactor pressure vessel assembly may include a housing surrounding a reactor core, steam separators, and a chimney. Inner surfaces of the chimney and reactor core define a conduit for transporting a two phase flow stream from the reactor core through the chimney to the steam separators. The housing defines an opening. An inner surface of the housing and outer surfaces of the chimney and reactor core define an annulus in fluid communication with the opening and conduit. A feedwater sparger in the housing is connected to the at least one opening and configured to deliver a sub-cooled feedwater into the annulus. A flow barrier structure between the chimney and the steam separators may force mixing between the sub-cooled feedwater and a downcomer fluid from the steam separators. An outer steam separator may be vertically over a portion of the flow barrier structure in a plan view.

    Apparatus for performing jet pump riser pipe repairs
    9.
    发明授权
    Apparatus for performing jet pump riser pipe repairs 失效
    用于执行喷射泵提升管修理的装置

    公开(公告)号：US6053652A

    公开(公告)日：2000-04-25

    申请号：US834315

    申请日：1997-04-15

    申请人： Gerald A. Deaver ,  Siamak Bourbour ,  Don Schrein ,  John G. Erbes

    发明人： Gerald A. Deaver ,  Siamak Bourbour ,  Don Schrein ,  John G. Erbes

    IPC分类号： G21C19/02 ,  F04F5/54 ,  F16D1/00 ,  G21C20060101 ,  G21C13/032 ,  G21C15/22 ,  G21C15/25 ,  G21C19/20

    CPC分类号： F16L13/06 ,  F16L55/179 ,  G21C15/25 ,  G21C19/207 ,  Y02E30/40 ,  Y10S403/09 ,  Y10T403/18 ,  Y10T403/4345 ,  Y10T403/4611 ,  Y10T403/5781

    摘要： Apparatus for supporting the lower riser assembly of a jet pump in a reactor pressure vessel (RPV) of a nuclear reactor. In one embodiment of the apparatus, the clamp assembly provides structural rigidity to the lower rise assembly. The clamp assembly includes a lower thermal sleeve clamp and a riser clamp. The lower thermal sleeve clamp is positioned adjacent an interface between the elbow and the thermal sleeve of the jet pump riser pipe assembly. The riser clamp is secured to the riser pipe of the jet pump riser pipe assembly at a location adjacent an interface between the riser pipe and the elbow. The lower thermal sleeve clamp and the riser clamp also are coupled to each other so that as the respective clamps are secured to the lower riser assembly.

    摘要翻译： 用于在核反应堆的反应堆压力容器（RPV）中支撑喷射泵的下提升管组件的装置。 在该装置的一个实施例中，夹具组件向下升组件提供结构刚性。 夹具组件包括下部热套筒夹和提升管夹。 下部热套筒夹具位于喷射泵提升管组件的弯头和热套筒之间的界面附近。 提升管夹在与提升管和肘部之间的界面相邻的位置处固定到喷射泵提升管组件的提升管。 下部热套筒夹具和提升管夹具也彼此联接，使得当相应的夹具固定到下部提升管组件时。

    Assemblies and methods for coupling piping to a safe end of a nuclear reactor
    10.
    发明授权
    Assemblies and methods for coupling piping to a safe end of a nuclear reactor 失效
    将管道连接到核反应堆安全端的组件和方法

    公开(公告)号：US6000731A

    公开(公告)日：1999-12-14

    申请号：US13534

    申请日：1998-01-26

    申请人： James E. Charnley ,  Gerald A. Deaver

    发明人： James E. Charnley ,  Gerald A. Deaver

    IPC分类号： F16L37/098 ,  F16L37/00

    CPC分类号： G21C13/032 ,  F16L37/098 ,  G21C13/02 ,  Y02E30/40

    摘要： Thermal sleeve assemblies for connecting a core spray line to a reactor safe end without welding. In one embodiment the thermal sleeve assembly includes a t-box junction, a thermal sleeve and a finger assembly. The t-box junction is attached core spray lines and the thermal sleeve. The finger assembly is coupled to the thermal sleeve and includes several fingers. The finger assembly includes a ring which is coupled to the thermal sleeve so that an opening in the ring is aligned with a bore extending through the thermal sleeve. The fingers are substantially L shaped and are attached to the ring so that when the ring is welded to the thermal sleeve second end the fingers extend from the thermal sleeve.

    摘要翻译： 用于将芯喷射管连接到反应堆安全端而不进行焊接的热套管组件。 在一个实施例中，热套筒组件包括一个t盒接头，一个热套筒和一个手指组件。 T型箱结连接有核心喷涂线和热套筒。 手指组件联接到热套筒并且包括若干指状物。 手指组件包括环，其连接到热套筒，使得环中的开口与延伸穿过热套筒的孔对准。 手指基本上是L形并且被附接到环上，使得当环被焊接到热套筒第二端时，手指从热套筒延伸。