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    Nuclear reactor plant with pressurized water reactor secured against bursting or rupture
    41.
    发明授权
    Nuclear reactor plant with pressurized water reactor secured against bursting or rupture 失效
    具有压水反应堆的核反应堆装置抵抗爆裂或破裂

    公开(公告)号：US4235672A

    公开(公告)日：1980-11-25

    申请号：US877742

    申请日：1978-02-14

    申请人： Elmar Harand ,  Eberhard Michel

    发明人： Elmar Harand ,  Eberhard Michel

    IPC分类号： F04D7/08 ,  F04D29/52 ,  F22B1/02 ,  F22B1/06 ,  F22B1/16 ,  G21C1/00 ,  G21C1/32 ,  G21C9/00 ,  G21D1/00 ,  G21D1/04 ,  G21C15/16

    CPC分类号： G21C1/322 ,  F04D29/528 ,  F22B1/023 ,  G21C9/001 ,  G21D1/04 ,  Y02E30/32

    摘要： In a nuclear reactor installation secured against rupture and having a pressurized water reactor, a straight-tube steam generator having a central ascending pipe, a coolant pump and lines connecting them in a primary circulatory loop, the coolant pump being installed in a primary chamber of the steam generator and forming with the latter a structural unit, the primary loop having hot and cold lines between a pressure vessel enclosing the reactor and the primary side of the steam generator, at least part of the hot and cold lines being united along the direction of their fluidic flow paths, the structural unit formed of the pump and the steam generator being upright with relatively short, straight and horizontal primary loop lines, and sheathing protective against rupture enclosing the pump, the steam generator and the lines of the primary loop, a tube bundle having a central passageway trough which the ascending pipe extends, an inlet chamber communicating with the top of the tube bundle, an outlet chamber communicating with the bottom of the tube bundle, tube support plates holding the bottom and top of the tube bundle, the ascending pipe feeding primary medium to the inlet chamber from which the primary medium is returned through the tube bundle to the outlet chamber, and a guidance elbow having a 90.degree.-bend extending through the outlet chamber, the guidance elbow connecting the ascending pipe and the hot line, the cold line communicating with the outlet chamber.

    摘要翻译： 在具有抗破裂和具有加压水反应器的核反应堆装置中，具有中央上升管，冷却剂泵和将它们连接在主循环回路中的管线的直管式蒸汽发生器，所述冷却剂泵安装在 所述蒸汽发生器和后者形成结构单元，所述主回路在包围所述反应器的压力容器和所述蒸汽发生器的初级侧之间具有冷热管线，所述冷热管线的至少一部分沿着所述方向 由泵和蒸汽发生器形成的结构单元具有相对较短的直线和水平的主回路线，并且包围防护包围泵，蒸汽发生器和主回路的管线的保护层， 管束，其具有上升管延伸的中心通道槽，与管束顶部连通的入口室 le，与管束底部连通的出口室，保持管束底部和顶部的管支撑板，上升管将主介质送入入口室，主介质从该入口室通过管束返回到 出口室和引导弯头，其具有延伸穿过出口室的90°弯头，引导弯头连接上升管道和热管线，冷管线与出口腔室连通。

    Steam generator for use in nuclear power plants
    42.
    发明授权
    Steam generator for use in nuclear power plants 失效
    蒸汽发生器用于核电厂

    公开(公告)号：US4230527A

    公开(公告)日：1980-10-28

    申请号：US850647

    申请日：1977-11-11

    申请人： Alexander Cella

    发明人： Alexander Cella

    IPC分类号： F22B1/02 ,  F22B37/20 ,  F28D7/06 ,  F28F9/013 ,  G21C15/16

    CPC分类号： F28D7/06 ,  F22B1/025 ,  F22B37/205 ,  F28F9/0136 ,  G21C15/16 ,  Y02E30/40

    摘要： An improved steam generator for use in a nuclear power plant of the pressurized water type in which a turbine generator is driven by the steam output of the steam generator to provide electrical power therefrom. The improvement comprises providing a vertically movable grid structure vertically extending within the interior of the lower housing portion of the steam generator through which individual tubes comprising a vertically extending tube bundle extend. The tube bundle has a tube sheet at one end thereof supporting the tube bundle for the tubes extending through the tube sheet in flow through communication with a heat exchange fluid inlet. The grid structure defines grid apertures therein through which the individual tubes extend with each of the grid apertures being in surrounding relationship with a portion of an associated one of the tubes. The grid structure is movable for a predetermined vertical extent, such as by hydraulic means, such as a piston, along the tubes for vertically displacing the means defining the grid apertures by a sufficient amount for removing the previously surrounded portion of each of the tubes from the associated grid apertures whereby an enhanced reading of the condition of the tubes at the previously surrounded portion is enabled. The steam generator may comprise vertically assemblable modules which are removably mounted together in sealing relationship, with the modules comprising a base module, a tube bundle module removably mountable on the base module in sealing relationship therewith and an uppermost drier module removably mountable on the tube bundle module in sealing relationship therewith whereby ready access to removal of the tube bundle module in situ from the nuclear power plant steam generator is facilitated.

    摘要翻译： 一种用于加压水型核电站的改进的蒸汽发生器，其中涡轮发电机由蒸汽发生器的蒸汽输出驱动以从其提供电力。 该改进包括提供垂直延伸的蒸汽发生器的下壳体部分的内部的垂直移动的格栅结构，通过该垂直方式，包括垂直延伸的管束的单独的管延伸。 管束在其一端具有管板，其支撑管束，用于通过与热交换流体入口连通而流过管板的管。 网格结构在其中限定了网格孔，各个管通过该孔径延伸，每个格栅孔与相关联的一个管的一部分处于环绕关系。 格栅结构可以例如通过诸如活塞的液压装置沿着管可移动，用于将限定栅格孔的装置垂直移位足够的量，以将每个管的先前包围的部分从 相关联的栅格孔，从而能够增强对先前包围的部分处的管的状态的读取。 蒸汽发生器可以包括垂直组装的模块，其以密封关系可拆卸地安装在一起，模块包括基座模块，管束模块，可拆卸地安装在与其密封的基座模块上，以及可拆卸地安装在管束上的最上部的干燥器模块 与其密封关系的模块，便于从原子能发电厂蒸汽发生器原位取出管束组件。

    Gas-liquid separator
    45.
    发明授权
    Gas-liquid separator 失效
    气液分离器

    公开(公告)号：US3603062A

    公开(公告)日：1971-09-07

    申请号：US3603062D

    申请日：1968-11-21

    申请人： GEN ELECTRIC

    发明人： ROBBINS CHARLES H ,  FITZSIMMONS GEORGE W ,  HUGHES ROBERT L ,  MOEN ROBERT L

    IPC分类号： B01D45/12 ,  G21C15/16

    CPC分类号： G21C15/16 ,  B01D45/12 ,  Y02E30/40

    摘要： A gas-liquid separating arrangement of high-capacity per unit size including a centrifugal separator for creating a gas vortex surrounded by a liquid vortex having a first discharge passage for receiving separated liquid and a second discharge passage for receiving and separating the gas and liquid of the boundary layer between the gas and liquid vortices and including a centrifugal preliminary dryer for receiving the gas vortex from the separator and for removing additional liquid.

    INTEGRAL REACTOR PRESSURE VESSEL TUBE SHEET
    50.
    发明申请
    INTEGRAL REACTOR PRESSURE VESSEL TUBE SHEET 有权

    公开(公告)号：US20210343432A1

    公开(公告)日：2021-11-04

    申请号：US17351213

    申请日：2021-06-17

    申请人： NuScale Power, LLC

    发明人： Tamas Liszkai ,  Seth Cadell ,  Alex Kruskamp ,  Matthew Mallet

    IPC分类号： G21C15/12 ,  G21C13/02 ,  G21C15/16

    摘要： A thermal control system for a reactor pressure vessel comprises a plate having a substantially circular shape that is attached to a wall of the reactor pressure vessel. The plate divides the reactor pressure vessel into an upper reactor pressure vessel region and a lower reactor pressure vessel region. Additionally, the plate is configured to provide a thermal barrier between a pressurized volume located within the upper reactor pressure vessel region and primary coolant located within the lower reactor pressure vessel region. One or more plenums provide a passageway for a plurality of heat transfer tubes to pass through the wall of the reactor pressure vessel. The plurality of heat transfer tubes are connected to the plate.