METHOD AND APPARATUS FOR A RISER PIPE REPAIR WITH COMPRESSION
    41.
    发明申请
    METHOD AND APPARATUS FOR A RISER PIPE REPAIR WITH COMPRESSION 有权
    用于升压管道修复的方法和装置

    公开(公告)号:US20120155598A1

    公开(公告)日:2012-06-21

    申请号:US12969845

    申请日:2010-12-16

    CPC classification number: G21C15/25 F22B1/143 G01N1/14 G21C17/017 Y02E30/31

    Abstract: A method and apparatus for repairing and/or reinforcing a Boiling Water Reactor (BWR) jet pump riser pipe. The repair includes attaching two collars to the riser pipe using match drilling to drill holes through the collars and the riser pipe and plugging the holes with expandable plugs. Support columns are attached to the collars. Brace supports are slideably attached to the support columns. Gaps between each brace support and its respective collar are then narrowed as ratchet bolts may apply a force that pulls downward on an upper collar and pulls upward on a lower collar, thereby exerting a compression force on the riser pipe. A clamp assembly may also be located between the two collars that applies a hoop force on the riser pipe.

    Abstract translation: 一种用于修复和/或加固沸水反应堆(BWR)喷射泵提升管的方法和装置。 修理包括使用匹配钻孔将两个套环连接到提升管,以穿过套环和提升管钻孔,并用可扩展插头堵塞孔。 支撑柱连接到项圈。 支撑支架可滑动地连接到支撑柱上。 然后,随着棘轮螺栓可以施加向上拉上一个上部轴环并在下部轴环上向上拉动,从而在提升管上施加压力,每个支撑支撑件及其相应套环之间的间隙变窄。 夹具组件也可以位于在提升管上施加环箍力的两个套环之间。

    Methods and apparatuses for clamping a jet pump sensing line support
    42.
    发明申请
    Methods and apparatuses for clamping a jet pump sensing line support 失效
    用于夹紧喷射泵感测线支架的方法和装置

    公开(公告)号:US20100266093A1

    公开(公告)日:2010-10-21

    申请号:US12385784

    申请日:2009-04-20

    CPC classification number: G21C15/25 Y02E30/31

    Abstract: Example embodiment clamps may be used to clamp two components together, with a degree of freedom of motion between the clamped components, including both rotational and translational motion. Example embodiment clamps may clamp a BWR jet pump sensing line to a diffuser as a repair or installation of a sensing line support. Example clamps may include a ball subassembly that holds a component and allows rotation and twisting of the component within the clamp. Example clamps may further include jaws holding the ball subassembly and a biasing element that permits tightening of the clamp.

    Abstract translation: 示例性实施例夹具可以用于将两个部件夹紧在一起,并且夹紧部件之间的运动自由度包括旋转和平移运动。 示例性实施例夹具可以将BWR喷射泵感测线夹紧到扩散器作为感测线支撑件的修复或安装。 示例性夹具可以包括保持部件并允许部件在夹具内的旋转和扭转的球子组件。 示例性夹具还可以包括夹持球子组件的夹爪和允许夹紧夹紧件的偏置元件。

    Jet pump auxiliary wedge
    43.
    发明授权
    Jet pump auxiliary wedge 有权
    喷射泵辅助楔

    公开(公告)号:US6052425A

    公开(公告)日:2000-04-18

    申请号:US217979

    申请日:1998-12-21

    Abstract: An auxiliary wedge apparatus configured to couple to the restrainer bracket of a jet pump assembly is described. In one embodiment, the auxiliary wedge apparatus includes a support block configured to couple to the restrainer bracket, and a wedge configured to slidingly couple to a wedge channel in the support block, and to engage the inlet mixer to restore a tight rigid fit-up of the jet pump components. The support block includes a wedge channel having tongues depending from the parallel sides of the channel and a hook shaped portion configured to receive the restrainer bracket. The support block also includes a lock screw to couple the support block to the restrainer bracket. The wedge includes grooves in the parallel sides of the wedge configured to slidingly engage the tongues extending in the wedge channel. The auxiliary wedge apparatus also includes a restraint arm depending from the support block configured to capture the existing set screw in the restrainer bracket to prevent the screw from completely unscrewing.

    Abstract translation: 描述了配置成联接到喷射泵组件的限制器支架的辅助楔形装置。 在一个实施例中,辅助楔形装置包括被配置为联接到限制器支架的支撑块和构造成滑动地联接到支撑块中的楔形通道并且与入口混合器接合以恢复紧密的刚性装配 的喷射泵部件。 支撑块包括具有从通道的平行侧悬垂的舌片的楔形通道和被构造成接收限制器支架的钩形部分。 支撑块还包括用于将支撑块联接到限制器支架的锁定螺钉。 楔形件包括在楔形物的平行侧中的凹槽,其被构造成滑动地接合在楔形通道中延伸的舌部。 辅助楔形装置还包括从支撑块悬垂的约束臂,其被配置为捕获限制器支架中的现有固定螺钉,以防止螺钉完全松开。

    Apparatus and methods for replacing jet pump diffusers in a nuclear
reactor
    44.
    发明授权
    Apparatus and methods for replacing jet pump diffusers in a nuclear reactor 失效
    用于更换核反应堆中的喷射泵扩散器的装置和方法

    公开(公告)号:US5805652A

    公开(公告)日:1998-09-08

    申请号:US684680

    申请日:1996-07-19

    CPC classification number: G21C15/25 G21Y2004/504 Y02E30/40

    Abstract: A replacement jet pump diffuser apparatus and method are described. In one embodiment, the replacement diffuser apparatus includes a conical section, a first cylindrical section, and a second cylindrical section. The conical section is welded to the first cylindrical section, and the first cylindrical section is welded to the second cylindrical section. A V-flange is formed at one end of the second cylindrical section. The assembly further includes an adapter having a V-flange formed at one end. The adapter is secured to the second cylindrical section by a band clamp which compresses the V-flanges into contact. The adapter further includes an engagement flange having a plurality of bores extending therethrough. L-bolts extend through the respective bores in the engagement flange, and each L-bolt includes an L-section and a threaded section. Respective nuts threadedly engage the threaded sections of the L-bolts. The L-section of each bolt contacts a lower surface of the shroud support plate.

    Abstract translation: 描述了替换喷射泵扩散装置和方法。 在一个实施例中,替换扩散装置包括圆锥形部分,第一圆柱形部分和第二圆柱形部分。 圆锥形部分焊接到第一圆柱形部分,并且第一圆柱形部分焊接到第二圆柱形部分。 V形凸缘形成在第二圆柱形部分的一端。 组件还包括在一端形成有V形凸缘的适配器。 适配器通过将V形凸缘压缩接触的带夹固定到第二圆柱形部分。 适配器还包括具有穿过其延伸的多个孔的接合凸缘。 L形螺栓延伸穿过接合凸缘中的各个孔,并且每个L形螺栓包括L形截面和螺纹部分。 各螺母螺纹接合L型螺栓的螺纹部分。 每个螺栓的L形部分接触护罩支撑板的下表面。

    Jet pump electro-nozzle
    45.
    发明授权
    Jet pump electro-nozzle 失效
    喷射泵电喷嘴

    公开(公告)号:US5444747A

    公开(公告)日:1995-08-22

    申请号:US239773

    申请日:1994-05-09

    Inventor: James H. Terhune

    Abstract: A method and a device for minimizing electrostatically enhanced deposition of charged particulates in the jet pump nozzles of operating BWR plants. The jet pump nozzle has an inner conducting surface which is electrically isolated from the main body of the nozzle. An electrical circuit is electrically coupled to the inner conducting surface of the nozzle. The electrical circuit is designed to electrically minimize charged-particle deposition at the nozzle surface exposed to a free-stream electrical potential, using a DC circuit with active element feedback to adjust the surface potential to minimize the net current to the inner conducting surface, thereby minimizing deposition.

    Abstract translation: 一种方法和装置,用于最大限度地减少在操作的BWR设备的喷射泵喷嘴中的带电粒子的静电增强沉积。 喷射泵喷嘴具有与喷嘴主体电绝缘的内导电表面。 电路电耦合到喷嘴的内导电表面。 电路被设计成使暴露于自由电位电位的喷嘴表面处的带电粒子沉积电化学最小化,使用具有有源元件反馈的DC电路来调节表面电位以最小化到内导电表面的净电流,由此 最小化沉积。

    Nuclear power plant
    46.
    发明授权
    Nuclear power plant 失效
    核电站

    公开(公告)号:US4879087A

    公开(公告)日:1989-11-07

    申请号:US152380

    申请日:1988-02-04

    CPC classification number: G21C1/084 G21C15/25 G21D3/04 G21D3/14 G21D5/06 Y02E30/31

    Abstract: Jet pumps and a feed water sparger are disposed in a reactor pressure vessel incorporating a core. A first feed water pipe supplies a portion of feed water to the jet pumps as their driving water. A second feed water pipe connected to the first feed water pipe supplies the remaining portion of the feed water to the feed water sparger. A first feed water heater is disposed in the first feed water pipe downstream of a connecting point of the first feed water pipe and the second feed water pipe. An amount of extracted steam introduced into the first feed water heater is controlled on the basis of a difference in the temperature between feed water flowing through the first feed water pipe and the feed water flowing through the second feed water pipe.

    Abstract translation: 喷射泵和给水喷射器设置在并入有核心的反应堆压力容器中。 第一给水管将一部分给水供应到喷射泵作为驱动水。 连接到第一给水管的第二给水管将给水的剩余部分供给给水分配器。 第一给水加热器设置在第一给水管和第二给水管的连接点下游的第一给水管中。 基于流过第一给水管的给水与流经第二给水管的给水之间的温度差来控制引入第一给水加热器的抽取蒸汽的量。

    Steam-assisted jet pump
    47.
    发明授权
    Steam-assisted jet pump 失效
    蒸汽辅助喷射泵

    公开(公告)号:US4847043A

    公开(公告)日:1989-07-11

    申请号:US147386

    申请日:1988-01-25

    CPC classification number: F04F5/466

    Abstract: An improved liquid jet pump for water is described in which the water issuing from the jet pump drive nozzle passes into a nozzle mixing chamber where steam is introduced to nozzle outflow. This steam, traveling in the same direction as and converging upon the liquid driving stream, is raised to high velocities. These uncommonly high velocities of steam are attained both as a result of passage through a converging/diverging nozzle and the action of condensation upon the passing liquid stream. The liquid driving stream is supplied at a temperature which promotes immediate condensation of the steam molecules of the high speed steam jet. A process of momentum exchange immediately occurs within the drive nozzle mixing chamber between the high-velocity steam and the parallel-moving slower liquid stream with momentum being transferred from the steam to the liquid driving stream. The liquid driving stream with its enhanced momentum is thereafter exhausted from the nozzle mixing chamber and used conventionally to drive the jet pump. Improved jet pump recirculation system is described for use with current and advanced boiling water nuclear reactors.

    Control of reactor coolant flow path during reactor decay heat removal
    48.
    发明授权
    Control of reactor coolant flow path during reactor decay heat removal 失效
    反应堆腐蚀除热过程中反应堆冷却剂流路的控制

    公开(公告)号:US4767594A

    公开(公告)日:1988-08-30

    申请号:US51332

    申请日:1987-05-19

    Abstract: An improved reactor vessel auxiliary cooling system for a sodium cooled nuclear reactor is disclosed. The sodium cooled nuclear reactor is of the type having a reactor vessel liner separating the reactor hot pool on the upstream side of an intermediate heat exchanger and the reactor cold pool on the downstream side of the intermediate heat exchanger. The improvement includes a flow path across the reactor vessel liner flow gap which dissipates core heat across the reactor vessel and containment vessel responsive to a casualty including the loss of normal heat removal paths and associated shutdown of the main coolant liquid sodium pumps. In normal operation, the reactor vessel cold pool is inlet to the suction side of coolant liquid sodium pumps, these pumps being of the electromagnetic variety. The pumps discharge through the core into the reactor hot pool and then through an intermediate heat exchanger where the heat generated in the reactor core is discharged. Upon outlet from the heat exchanger, the sodium is returned to the reactor cold pool. The improvement includes placing a jet pump across the reactor vessel liner flow gap, pumping a small flow of liquid sodium from the lower pressure cold pool into the hot pool. The jet pump has a small high pressure driving stream diverted from the high pressure side of the reactor pumps. During normal operation, the jet pumps supplement the normal reactor pressure differential from the lower pressure cold pool to the hot pool. Upon the occurrence of a casualty involving loss of coolant pump pressure, and immediate cooling circuit is established by the back flow of sodium through the jet pumps from the reactor vessel hot pool to the reactor vessel cold pool. The cooling circuit includes flow into the reactor vessel liner flow gap immediate the reactor vessel wall and containment vessel where optimum and immediate discharge of residual reactor heat occurs.

    Abstract translation: 公开了一种用于钠冷核反应堆的改进的反应堆辅助冷却系统。 钠冷核反应堆是具有将中间热交换器的上游侧的反应器热池和中间热交换器的下游侧的反应堆冷库分离的反应容器衬套的类型。 改进之处包括穿过反应堆容器衬里流动间隙的流动路径,其消除跨过反应堆容器的核心热量,以及响应于伤员的容纳容器,包括正常的散热路径的损失和主冷却剂液体钠泵的关联。 在正常运行中,反应堆容器冷库是冷却剂液体钠泵的吸入口的入口,这些泵是电磁式的。 泵通过芯排出到反应堆热池中,然后通过中间热交换器排放反应堆堆芯中产生的热量。 在热交换器出口处,钠返回到反应堆冷库。 该改进包括将喷射泵放置在反应器容器衬里流动间隙上,将低流量的液体钠从低压冷水池泵入热水池。 喷射泵具有从反应堆泵的高压侧转向的小的高压驱动流。 在正常运行期间,喷射泵补充了从低压冷水池到热水池的正常反应堆压力差。 在发生涉及冷却液泵压力损失的事故发生时,通过喷射泵从反应堆容器热池向反应堆容器冷库的反向流动建立立即冷却回路。 冷却回路包括立即进入反应堆容器衬里流动间隙的流动反应器壁和容纳容器,其中发生残余反应堆热的最佳和立即排放。

    Emergency core cooling system
    50.
    发明授权
    Emergency core cooling system 失效
    应急核心冷却系统

    公开(公告)号:US4367194A

    公开(公告)日:1983-01-04

    申请号:US189534

    申请日:1980-09-22

    Abstract: A liquid metal cooled fast breeder reactor provided with an emergency core cooling system includes a reactor vessel which contains a reactor core comprising an array of fuel assemblies and a plurality of blanket assemblies. The reactor core is immersed in a pool of liquid metal coolant. The reactor also includes a primary coolant system comprising a pump and conduits for circulating liquid metal coolant to the reactor core and through the fuel and blanket assemblies of the core. A converging-diverging venturi nozzle with an intermediate throat section is provided in between the assemblies and the pump. The intermediate throat section of the nozzle is provided with at least one opening which is in fluid communication with the pool of liquid sodium. In normal operation, coolant flows from the pump through the nozzle to the assemblies with very little fluid flowing through the opening in the throat. However, when the pump is not running, residual heat in the core causes fluid from the pool to flow through the opening in the throat of the nozzle and outwardly through the nozzle to the assemblies, thus providing a means of removing decay heat.

    Abstract translation: 提供有应急芯冷却系统的液态金属冷却的快速增殖反应器包括反应器容器,其包含反应堆堆芯,该堆芯包括燃料组件阵列和多个橡皮布组件。 将反应堆芯浸入液态金属冷却剂池中。 反应器还包括一个主要的冷却剂系统,其包括泵和用于将液体金属冷却剂循环到反应堆堆芯并通过核心的燃料和橡皮布组件的导管。 在组件和泵之间提供具有中间喉部的会聚发散文丘里喷嘴。 喷嘴的中间喉部设置有至少一个与液体钠液体流体连通的开口。 在正常操作中,冷却剂从泵通过喷嘴流到组件,流体流过喉部的开口很少。 然而,当泵没有运行时,芯中的残余热量使得来自池的流体流过喷嘴喉部的开口,并通过喷嘴向外流到组件,从而提供去除腐蚀热的手段。

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