PASSIVE COOLING SYSTEM OF CONTAINMENT BUILDING AND NUCLEAR POWER PLANT COMPRISING SAME
    1.
    发明申请
    PASSIVE COOLING SYSTEM OF CONTAINMENT BUILDING AND NUCLEAR POWER PLANT COMPRISING SAME 审中-公开
    含有建筑物的被动冷却系统和包含其的核电厂

    公开(公告)号:US20170004892A1

    公开(公告)日:2017-01-05

    申请号:US15100224

    申请日:2014-12-02

    IPC分类号: G21C15/18 G21D1/02 G21C9/004

    摘要: The present invention discloses a passive cooling system of a containment building, to which a plate-type heat exchanger is applied. A passive cooling system of a containment building comprises: a containment building; a plate-type heat exchanger provided to at least one of the inside and the outside of the containment building and comprising channels respectively provided to the both sides of a plate so as to be arranged dividedly from each other such that the plate-type heat exchanger carries out mutual heat exchange between the internal atmosphere of the containment building and a heat exchange fluid while maintaining a pressure boundary; and a pipe connected to the plate-type heat exchanger by penetrating the containment building so as to form the path of the internal atmosphere of the containment building or the heat exchange fluid.

    摘要翻译: 本发明公开了一种安全壳建筑物的被动冷却系统,其中应用了板式热交换器。 遏制建筑物的被动冷却系统包括:遏制建筑物; 设置在容纳建筑物的内部和外部的至少一个的板式热交换器,并且包括分别设置在板的两侧的通道,以便彼此分开布置,使得板式热交换器 在保持压力边界的同时,在容纳建筑物的内部气氛与热交换流体之间进行相互热交换; 以及通过穿透容纳建筑​​物而连接到板式热交换器以形成容纳建筑物或热交换流体的内部气氛的路径的管道。

    PASSIVE HEAT REMOVAL SYSTEM AND NUCLEAR POWER PLANT INCLUDING SAME

    公开(公告)号:US20170148533A1

    公开(公告)日:2017-05-25

    申请号:US15327355

    申请日:2015-07-22

    IPC分类号: G21C15/18

    摘要: The present invention relates to a passive heat removal system which circulates cooling fluid via a main water supply line, connected to the lower inlet of a steam generator, and a main steam pipe, connected to the top outlet of the steam generator, to the steam generator, in order to remove sensible heat of a reactor coolant system and residual heat of a core, the passive heat removal system comprising: supplementary equipment for receiving surplus cooling fluid or supplying supplementary cooling fluid in order to maintain the flow rate of the cooling fluid within a predetermined range, wherein the supplementary equipment comprises: a supplementary tank, installed at a predetermined height between the lower inlet and the top outlet of the steam generator, for receiving the surplus cooling fluid or supplying the supplementary cooling fluid, passively, depending on the flow rate of the cooling fluid; a first connection pipe, connected to the main steam pipe and the supplementary tank, for forming a flow path to allow the cooling fluid, exhausted to the main steam pipe from the steam generator, to flow to the supplementary tank; and a second connection pipe connected to the supplementary tank and the main water supply pipe for forming a supply flow path of the supplementary cooling fluid supplied from the supplementary tank.

    NUCLEAR REACTOR COOLANT PUMP AND NUCLEAR POWER PLANT HAVING SAME
    4.
    发明申请
    NUCLEAR REACTOR COOLANT PUMP AND NUCLEAR POWER PLANT HAVING SAME 审中-公开
    核反应堆冷却泵和具有相同功能的核电厂

    公开(公告)号:US20160260509A1

    公开(公告)日:2016-09-08

    申请号:US15030578

    申请日:2014-11-25

    IPC分类号: G21C15/24 G21C15/18 G21D1/04

    摘要: The present invention discloses a nuclear reactor coolant pump that does not rely on an electric motor, but is operated by means of driving force generated inside a nuclear power plant, so a to be capable of maintaining the safety of the nuclear reactor when the nuclear reactor is operating normally and also in the event of an accident in the nuclear reactor. The nuclear reactor coolant pump comprises: a pump impeller rotatably installed in a first fluid passage of a nuclear reactor coolant system to circulate a first fluid inside the nuclear reactor coolant system; a drive unit receiving steam from a steam generator to generate driving force to rotate the pump impeller, and rotating about the same rotating shaft as the pump impeller to transfer the generated driving force to the pump impeller; and a steam supplying unit forming a passage between the steam generator and the drive unit to supply at least a portion of the steam released from the steam generator to the drive unit.

    摘要翻译: 本发明公开了一种核反应堆冷却剂泵,其不依赖于电动机,而是通过在核电厂内产生的驱动力来操作,因此当核反应堆能够保持核反应堆的安全性时 正常运行,并且在核反应堆发生事故时也是如此。 核反应堆冷却剂泵包括:可旋转地安装在核反应堆冷却剂系统的第一流体通道中的泵叶轮,以使核反应堆冷却剂系统内的第一流体循环; 驱动单元,其接收来自蒸汽发生器的蒸汽,以产生用于使所述泵叶轮旋转的驱动力,并且围绕与所述泵叶轮相同的旋转轴旋转以将所产生的驱动力传递到所述泵叶轮; 以及蒸汽供给单元,其形成在所述蒸汽发生器和所述驱动单元之间的通道,以将从所述蒸汽发生器释放的蒸汽的至少一部分供给到所述驱动单元。