DEVICE FOR REMOVING FOREIGN MATTERS IN NUCLEAR REACTOR VESSEL

    公开(公告)号:US20180358140A1

    公开(公告)日:2018-12-13

    申请号:US15838399

    申请日:2017-12-12

    发明人: Liping Deng

    IPC分类号: G21D1/04

    CPC分类号: G21D1/04 G21C19/20 G21C19/307

    摘要: A device for removing foreign matters in nuclear reactor vessel comprises a suction pipe; a suction opening structure disposed at a lower end of the suction pipe, wherein the suction opening structure has a suction opening thereon; an electric valve disposed at a connection of the suction pipe and the flared pipe; and a filter mesh and a suction pump sequentially located in the suction pipe and above the electric valve; wherein a water inlet of the suction pump is communicated with the suction opening, a water outlet of the suction pump is communicated with the outside space of the suction pipe though a drainage pipe, and the electric valve is controlled by the touch switch. The device has a simple structure and is easy for operation, through which foreign matters can be taken out of the reactor vessel even though their specific location is not known.

    DRAINAGE APPARATUS AND DRAINAGE METHOD FOR REACTOR COOLANT SYSTEM
    6.
    发明申请
    DRAINAGE APPARATUS AND DRAINAGE METHOD FOR REACTOR COOLANT SYSTEM 审中-公开
    排水装置和排水方法的反应器冷却系统

    公开(公告)号:US20090154635A1

    公开(公告)日:2009-06-18

    申请号:US12190016

    申请日:2008-08-12

    IPC分类号: G21D1/04

    CPC分类号: G21D1/04 G21C15/00 Y02E30/40

    摘要: A drainage apparatus and a drainage method for a reactor coolant system are disclosed. According to the drainage apparatus and the drainage method, the gravity drainage procedure for performing the decomposition maintenance of a main valve forming the pressure boundary part between the RCS and the safety injection system is improved by a forced drainage procedure using a drainage pump, and there are the effects that working period for a planned preventive maintenance is shortened, liquid waste of a coolant of the reactor is not generated, reprocessing costs are decreased, and the economical efficiency and the safety of the nuclear power plant are improved.

    摘要翻译: 公开了用于反应堆冷却剂系统的排水装置和排水方法。 根据排水装置和排水方法,通过使用排水泵的强制排水程序,提高了形成RCS和安全注射系统之间的压力边界部分的主阀的分解维护的重力排水程序,并且在那里 是缩短计划预防性维护工作时间的效果,不会产生反应堆冷却液的液体废液,后处理成本降低,核电厂的经济效益和安全性得到提高。

    Thermal fatigue prevention apparatus for high temperature pump
    7.
    发明授权
    Thermal fatigue prevention apparatus for high temperature pump 失效
    高温泵热疲劳防护装置

    公开(公告)号:US5333991A

    公开(公告)日:1994-08-02

    申请号:US051294

    申请日:1993-04-23

    申请人: Hiroyuki Kato

    发明人: Hiroyuki Kato

    摘要: A thermal fatigue prevention apparatus for a high temperature pump which includes an impeller in a high temperature pump casing, a pump shaft rotatably supported by a journal of a submerged bearing and projecting from a shaft through hole of a casing cover, and a shaft sealing device. The shaft sealing device is enclosed with a shaft sealing chamber which is supplied with a low temperature seal purging liquid, and a part of the seal purging liquid flows into the pump casing through the shaft through hole. A heater is provided within the high temperature pump, the heater raises the temperature of the low temperature seal purging liquid before the seal purging liquid flows into the pump casing by using the high temperature pumping liquid.

    摘要翻译: 一种用于高温泵的热疲劳防止装置,其包括在高温泵壳体中的叶轮,由轴承座的轴孔旋转地支撑并从壳体盖的轴通孔突出的泵轴,以及轴封装置 。 轴封装置被封闭在具有低温密封清洗液的轴封室中,一部分密封清洗液通过轴贯通孔流入泵壳体。 在高温泵内设置有加热器,在使用高温泵送液体之前,加热器提高低温密封清洗液的温度,然后密封清洗液体流入泵壳体。

    Pressurized water reactor plant
    8.
    发明授权
    Pressurized water reactor plant 失效
    加压水反应堆厂

    公开(公告)号:US5331677A

    公开(公告)日:1994-07-19

    申请号:US22940

    申请日:1993-02-26

    申请人: Tsuyoshi Matsuoka

    发明人: Tsuyoshi Matsuoka

    CPC分类号: G21C15/18 G21C1/086 Y02E30/32

    摘要: A pressurized water reactor plant includes a reactor vessel (1), a reactor coolant pump (5) having an inlet connected by coolant pipe (2) to an outlet of the reactor vessel, a steam generator (10) having an inlet connected by a high-temperature side pipe (4) to the outlet of the pump (5) and an outlet connected by low-temperature side pipe (6) to an inlet of the reactor vessel. The steam generator has a horizontally extending shell (11) in the interior of which are horizontal U-shaped tube bundles (30) supported on tube support plates (20) and a pair of separator plates (18) which divide the interior of the shell into downcomer space (19). A partition plate (21) divides the interior of the shell into a U-shaped tube region (16) and a straight tube region (17). A moisture separator (27) is disposed above the heat transfer tubes (15) and a drain pipe (28) extends therefrom for draining impurities from the moisture separator to the U-shaped tube region (16) to which blowdown pipe (26) is connected.

    摘要翻译: 压力水反应堆设备包括反应器容器(1),反应堆冷却剂泵(5),其具有通过冷却剂管(2)连接到反应器容器的出口的入口,蒸汽发生器(10),其具有通过 高温侧管(4)到泵(5)的出口以及通过低温侧管(6)连接到反应器容器入口的出口。 蒸汽发生器具有水平延伸的壳体(11),其内部是支撑在管支撑板(20)上的水平U形管束(30)和分隔壳体内部的一对隔板(18) 进入降液管空间(19)。 分隔板(21)将壳体的内部分成U形管区域(16)和直管区域(17)。 水分分离器(27)设置在传热管(15)的上方,排水管(28)从其中延伸出来,用于将杂质从湿气分离器排出到排放管(26)所在的U形管区(16) 连接的。

    Apparatus for facilitating the servicing of inverted canned pump motors
having limited access space and restricted access time especially in
nuclear power plants
    9.
    发明授权
    Apparatus for facilitating the servicing of inverted canned pump motors having limited access space and restricted access time especially in nuclear power plants 失效
    用于便于对具有有限的进入空间和限制的进入时间的反向罐式泵马达的维修的装置,特别是在核电站中

    公开(公告)号:US5061432A

    公开(公告)日:1991-10-29

    申请号:US489134

    申请日:1990-03-05

    申请人: John M. Matusz

    发明人: John M. Matusz

    CPC分类号: G21C19/02 G21C19/207

    摘要: Service apparatus is provided for a large inverted canned motor pump installed above a floor and beneath a large steam generator in a fossil or nuclear power plant with limited access space and with limited access time at least in the case of nuclear power plants. The canned motor pump has a pump casing and a depending motor having a flange secured to a pump casing flange by a plurality of tensioned studs with tightened nuts.The service apparatus includes a maintenance cart having a height greater than the height of the motor casing beneath the motor flange and further having a generally U-shaped frame with an open vertical side that permits the cart to be moved horizontally such that the cart frame can be moved under the pump casing to surround the depending motor.Three electromechanical actuators are supported by the cart frame and each has a downwardly extending translating arm engageable with respective motor lugs near the bottom of the motor. The translating arms are operated to support, raise and lower the motor with its axis vertical or at an incline to the vertical. The motor is supported on top of the cart frame prior to raising the motor to its installed position and after the motor has been released from its installed position and lowered to the cart.A work platform is provided on top of the cart by a plate welded to the top of the framework platform and a removable platform section extending across the open side of the frame. A personnel platform is provided on the cart art an elevation below the work platform. The personnel platform includes a swing down section on the bight cart side, two fixed sections on the two leg sides of the cart and a removable section on the open cart side. Rollers are provided on the bottom of the cart frame to facilitate horizontal cart movement along the floor.

    摘要翻译: 提供的服务设备用于安装在地板上方并位于化石或核电站内的大型蒸汽发生器下方的大型倒置罐头电动机,其具有有限的进入空间,并且至少在核电站的情况下具有有限的进入时间。 密封电动泵具有泵壳体和悬挂式电动机,其具有通过多个具有拧紧螺母的张紧螺柱固定到泵壳体凸缘的凸缘。 该维修装置包括维护车,其具有高于电动机法兰下方的电动机壳体的高度的高度,并且还具有大致U形的框架,该车架具有敞开的垂直侧,允许车水平移动,使得车架可以 在泵壳下方移动以包围立式电机。 三个机电致动器由推车架支撑,并且每个具有向下延伸的平移臂,该平移臂可与马达底部附近的相应的马达接头接合。 平移臂被操作以支撑,升高和降低电动机的轴线垂直或垂直于倾斜。 在将电动机升高到其安装位置之前,以及在电动机从其安装位置释放并降低到推车之后,电动机被支撑在车架的顶部。 通过焊接在框架平台顶部的板和横跨框架开口侧延伸的可拆卸平台部分,在推车的顶部提供工作平台。 在工具平台下方提供了一个人员平台,在手推车艺术中提供了一个高程。 人员平台包括扶手车侧的摆动部分,推车的两个腿侧上的两个固定部分和敞开车辆侧的可拆卸部分。 滚筒设置在推车架的底部,以便于沿着地面移动水平推车。

    Reactor coolant pump auxiliary flexible vacuum seal for reactor coolant
system vacuum degasification
    10.
    发明授权
    Reactor coolant pump auxiliary flexible vacuum seal for reactor coolant system vacuum degasification 失效
    反应堆冷却液泵辅助柔性真空密封,用于反应堆冷却剂系统真空脱气

    公开(公告)号:US4981304A

    公开(公告)日:1991-01-01

    申请号:US294331

    申请日:1989-01-06

    摘要: An auxiliary flexible vacuum seal for preparing a reactor coolant pump for vacuum degasification of the reactor coolant system employs a flexible boot member having a pair of longitudinally-displaced opposite open end portions and a pair of side-by-side longitudinally-extending side portions in the form of flanges defining a split in the boot member along a side thereof and extending between the open end portions for allowing flexing of the boot member between open and closed side configurations to permit its installation and removal on and from the pump. The seal also employs clamping brackets and fasteners for releasably and sealably clamping together the flanges of the boot member at the split to retain the boot member in its closed configuration. The seal further includes a pair of circumferentially-extending sealing portions formed integrally on the interior of the boot member at opposite open end portions thereof for sealably engaging the pump when the boot member is flexed to its closed configuration to thereby permit generation of a vacuum seal condition between the boot member and the pump. Preferably, a boot support member is disposed within the boot member between the boot member and the pump for supporting the boot member when in its closed configuration.