Jet pump wedge locking support apparatus
    21.
    发明授权
    Jet pump wedge locking support apparatus 失效
    喷射泵楔形锁定支撑装置

    公开(公告)号:US5978433A

    公开(公告)日:1999-11-02

    申请号:US217980

    申请日:1998-12-21

    IPC分类号: G21C15/25 G21C19/02

    摘要: A wedge locking support apparatus that applies a downward preload force to a jet pump inlet mixer gravity wedge and is remotely installable without disassembly of the jet pumps is described. The downward force supplied by the wedge locking support apparatus supplements the force supplied by the weight of the gravity wedge and improves the lateral support provided to the inlet mixer by the gravity wedge. The wedge locking support apparatus includes an upper leaf spring assembly configured to engage the gravity wedge bracket, a lower leaf spring assembly slidably coupled to the upper leaf spring assembly and configured to engage the top of the wedge, and a jack bolt coupled to the upper and lower assemblies.

    摘要翻译: 描述了一种楔形锁定支撑装置,其将向下的预加载力施加到喷射泵入口混合器重力楔并且可远程安装而不拆卸喷射泵。 由楔形锁定支撑装置提供的向下的力补充由重力楔的重量提供的力并改善由重力楔提供给入口混合器的侧向支撑。 楔形锁定支撑装置包括构造成接合重力楔形支架的上部板簧组件,可滑动地联接到上部板簧组件并被构造成接合楔形物的顶部的下部板簧组件,以及联接到上部板簧上部的千斤顶螺栓 和下部组件。

    Coolant pipe blocking device for use in a nuclear power plant
    23.
    发明授权
    Coolant pipe blocking device for use in a nuclear power plant 失效
    用于核电站的冷却管堵塞装置

    公开(公告)号:US5867547A

    公开(公告)日:1999-02-02

    申请号:US849109

    申请日:1997-05-28

    申请人: Se Yup Lee

    发明人: Se Yup Lee

    摘要: A coolant pipe blocking device for use in a nuclear power plant is provided to temporarily choke up a coolant inlet pipe to thereby inhibit fluid communication between a reactor and a steam generator, the steam generator having a coolant chamber in communication with the reactor via the coolant inlet pipe and a manway providing access to the coolant chamber. The pipe blocking device includes a plurality of hub segments(42-48) arranged along a longitudinal axis substantially with a uniform spacing to one another and an elongated, flexible, support rod(50) extending in a coaxial relationship with the longitudinal axis for interconnecting and keeping spaced apart the hub segments. A plurality of bladders(52-60) are arranged in an end-to-end relationship with respect to one another and attached to the hub segments to define a series of hermetically sealed air chambers. Each of the bladders is so sized as to, when deflated, move freely into and out of the coolant inlet pipe via the manway and, when inflated, to make a fluid-tight contact with an inner surface of the coolant inlet pipe. In addition, the pile blocking device has a plurality of air hoses(64-68) corresponding to the bladders and projecting respectively into the air chambers to allow air to be evacuated out of and admitted into the air chambers therethrough.

    摘要翻译: PCT No.PCT / KR95 / 00151 Sec。 371日期1997年5月28日 102(e)日期1997年5月28日PCT提交1995年11月20日PCT公布。 公开号WO96 / 17356 日期1996年6月6日提供用于核电站的冷却剂管阻塞装置,以暂时扼制冷却剂入口管,从而阻止反应堆和蒸汽发生器之间的流体连通,所述蒸汽发生器具有与 反应器经由冷却剂入口管和通向冷却剂室的通道。 管道阻塞装置包括沿着纵向轴线布置的多个毂段(42-48),所述毂段基本上彼此具有均匀的间隔,以及细长的,柔性的支撑杆(50),其与纵向轴线以同轴关系延伸,用于互连 并保持间隔开的毂段。 多个囊(52-60)相对于彼此以端对端的关系布置,并且附接到轮毂段以限定一系列气密密封的空气室。 每个气囊的尺寸如此大,当放气时,经由人行道自由地进入和离开冷却剂入口管,并且当膨胀时,与冷却剂入口管的内表面形成流体密封的接触。 此外,打桩装置具有与气囊相对应的多个气软管(64-68),并分别突出到空气室中以允许空气从空气室排出并进入空气室。

    Replacement core shroud assembly for a boiling water reactor
    24.
    发明授权
    Replacement core shroud assembly for a boiling water reactor 失效
    用于沸水反应器的替换芯套管组件

    公开(公告)号:US5828713A

    公开(公告)日:1998-10-27

    申请号:US948269

    申请日:1997-10-09

    摘要: A method of replacing a boiling water reactor core shroud includes the steps of removing at least a portion of the existing core shroud from supporting structure in the reactor vessel, lowering a replacement shroud into the reactor vessel, positioning the replacement shroud on the supporting structure such that a bottom portion of the replacement shroud mates cooperatively with the supporting structure to limit lateral movement of the replacement shroud relative to the reactor vessel, and holding the replacement shroud assembly in place by applying axially compressive forces to the shroud in the direction of the supporting structure. If the existing core shroud is secured by welds, a parting cut is made to remove the shroud and the replacement shroud is held in place by securing a plurality of tie rods between sites on the replacement shroud and the supporting structure at a respective plurality of angularly spaced locations about the shroud periphery. Existing safe end assemblies welded to core spray supply piping in the reactor vessel are removed and replaced with new safe end assemblies carrying components which mechanically couple with core spray supply piping carried by the replacement core shroud.

    摘要翻译: 更换沸水反应堆堆芯护罩的方法包括以下步骤:将现有的芯护罩的至少一部分从反应器容器中的支撑结构移除,将更换的护罩降低到反应堆容器中,将更换的护罩定位在支撑结构上 替换护罩的底部部分与支撑结构协同配合以限制替换护罩相对于反应堆容器的横向移动,并且通过沿支撑件的方向对护罩施加轴向压缩力来将替换护罩组件保持在适当位置 结构体。 如果现有的芯护罩通过焊缝固定,则分离切口被制成以移除护罩,并且通过将多个拉杆固定在更换护罩和支撑结构上的位置之间,将多个拉杆固定在相应的多个角度 围绕护罩周边的间隔位置。 焊接到反应堆容器中的核心喷雾供应管道的现有安全端组件被移除并且被新的安全端组件替代,该新安全端组件承载与由替换的芯护罩承载的芯喷射供应管道机械耦合的部件。

    Methods and apparatus for securing components in nuclear reactors
    25.
    发明授权
    Methods and apparatus for securing components in nuclear reactors 失效
    确保核反应堆部件的方法和装置

    公开(公告)号:US5803688A

    公开(公告)日:1998-09-08

    申请号:US599128

    申请日:1996-02-09

    CPC分类号: G21C19/26 F16B13/0808

    摘要: Methods and apparatus for securing a tie rod to a shroud support structure are described. One embodiment of the apparatus is a toggle bolt assembly including a toggle bolt body having an upper threaded portion and a lower toggle engaging portion. A toggle is rotatably secured to the toggle bolt body at the lower toggle engaging portion. A crimp nut including a threaded nut portion and a crimp collar is threadedly secured to the upper threaded portion of the toggle bolt body. Such toggle bolt assembly also includes a sleeve sized to have at least a portion of the toggle bolt body and the toggle located therein. The sleeve has a toggle opening so that the toggle can rotate from a first position in which the toggle is substantially located within the sleeve to a second position in which surface engaging portions of the toggle extend beyond the sleeve. A lower portion of the sleeve has a toggle rotation surface to facilitate rotation of the toggle.

    摘要翻译: 描述了用于将拉杆固定到护罩支撑结构的方法和装置。 该装置的一个实施例是一种肘节螺栓组件,其包括具有上部螺纹部分和下部肘节接合部分的肘节螺栓本体。 肘节在下肘杆接合部分处可旋转地固定到肘节螺栓本体。 包括螺母部分和压接套环的压接螺母螺纹固定到肘节螺栓本体的上部螺纹部分。 这种肘节螺栓组件还包括尺寸适于具有肘节螺栓本体和肘杆的至少一部分的套筒。 套筒具有肘节开口,使得肘节可以从其中肘节基本上位于套筒内的第一位置旋转到第二位置,在第二位置,肘节的表面接合部分延伸超过套筒。 套筒的下部具有肘节旋转表面以便于肘节的旋转。

    Removable retrofit shroud for a boiling water nuclear reactor and
associated method
    28.
    发明授权
    Removable retrofit shroud for a boiling water nuclear reactor and associated method 失效
    沸水核反应堆可拆卸改装护罩及相关方法

    公开(公告)号:US5583899A

    公开(公告)日:1996-12-10

    申请号:US373377

    申请日:1995-01-17

    申请人: Charles W. Relf

    发明人: Charles W. Relf

    摘要: In a pressure vessel of a nuclear reactor containing a core assembly enclosed within a core shroud, the shroud spaced radially inwardly of a side wall of the pressure vessel, and an annular pump deck welded in a place in an annular radial space between the core shroud and the side wall of the pressure vessel. The shroud provided with a radially outwardly extending flange seated on and removably secured to the pump deck. Wedge elements are interposed between flange portions and the side wall.

    摘要翻译: 在核反应堆的压力容器中,该核反应堆包含封闭在核心护罩内的芯组件,护罩与压力容器的侧壁径向向内隔开,以及环形泵座,其焊接在芯套之间的环形径向空间 和压力容器的侧壁。 护罩设有一个径向向外延伸的凸缘,该法兰可以安装在可拆卸地固定在泵甲板上。 楔形元件插在凸缘部分和侧壁之间。

    Reactor core shroud repair with tapered pins
    29.
    发明授权
    Reactor core shroud repair with tapered pins 失效
    反应堆芯护罩修复与锥形针

    公开(公告)号:US5521951A

    公开(公告)日:1996-05-28

    申请号:US311300

    申请日:1994-09-23

    摘要: A method and an apparatus for repairing a shroud in which one or more shroud girth seam welds have experienced SCC. The method involves the placement of a plurality of brackets around the outer circumference of the shroud at a plurality of azimuthal positions. Each bracket has circular holes for receiving respective tapered pin assemblies. Corresponding circular holes are machined in the shroud wall at positions which will align with the holes in the bracket. Each tapered pin assembly is inserted and then manipulated remotely from outside the shroud. Each tapered pin assembly consists of three types of parts: a threaded tapered pin, a slotted sleeve with a tapered bore, and a threaded nut. When fully installed, the tapered pin is encased by the sleeve. As the tapered pin is tensioned, the sleeve exerts a radially outwardly directed contact pressure on the cylindrical surface of the aligned circular holes respectively formed in the bracket and shroud.

    摘要翻译: 一种用于修理护罩的方法和装置,其中一个或多个护罩环围缝焊缝经历了SCC。 该方法包括在多个方位角位置上围绕护罩的外周布置多个支架。 每个支架具有用于接收各个锥形销组件的圆形孔。 相应的圆孔在护罩壁上加工成与支架中的孔对齐的位置。 插入每个锥形销组件,然后从护罩外部远程操作。 每个锥形销组件由三种类型的部件组成:螺纹锥形销,带锥形孔的开槽套管和螺纹螺母。 当完全安装时,锥形销被套筒包住。 当锥形销被张紧时,套筒在分别形成在支架和护罩中的对准的圆形孔的圆柱形表面上施加径向向外的接触压力。

    Process for electrochemical machining
    30.
    发明授权
    Process for electrochemical machining 失效
    电化学加工工艺

    公开(公告)号:US5516401A

    公开(公告)日:1996-05-14

    申请号:US271470

    申请日:1994-07-07

    摘要: An electrolyte is circulated between the surface to be machined, raised to an anode potential, and a tool electrode (9') raised to a cathode potential. The electrolyte contains lithium nitrate as a unique active product with a concentration of between 20 g/l and 2350 g/l and preferably between 50 g/l and 250 g/l. The process can be applied to the machining of the surface of any metallic component and in particular to the machining of the internal surface of tubular components (5) such as penetrations in the vessel bottom or closure head of a nuclear reactor; in this case the electrochemical machining cell consists of a cylindrical tool electrode (9') placed inside the component to be machined.

    摘要翻译: 电解质在待加工表面之间循环,升高至阳极电位,并将工具电极(9')升高至阴极电位。 电解液含有浓度为20g / l至2350g / l,优选为50g / l至250g / l的独特活性产物的硝酸锂。 该方法可以应用于任何金属部件的表面的加工,特别是加工管状部件(5)的内表面,例如在核反应堆的容器底部或封闭头中的穿透; 在这种情况下,电化学加工单元由放置在待加工部件内的圆柱形工具电极(9')组成。