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    Passive residual heat removal system and nuclear power plant equipment
    65.
    发明公开
    Passive residual heat removal system and nuclear power plant equipment 有权
    被动Nachwärmeabfuhrsystem

    公开(公告)号：EP2725582A1

    公开(公告)日：2014-04-30

    申请号：EP13189648.2

    申请日：2013-10-22

    申请人： Hitachi-GE Nuclear Energy, Ltd.

    发明人： Ikegawa, Tomohiko ,  Kito, Kazuaki

    IPC分类号： G21C9/012 ,  G21C15/18

    CPC分类号： G21C15/18 ,  G21C9/012 ,  Y02E30/40

    摘要： Disclosed is a passive residual heat removal system and nuclear power plant equipment configured to alleviate a rise in an internal pressure of a primary containment vessel (17), even if fluid line breakage of a reactor pressure vessel (15) occurs and for whatever reason, supply of a coolant (2) to the reactor pressure vessel (15) fails.
    This invention includes: a heat exchanger (1) provided at a position higher than a primary containment vessel (17); a condensate storage tank (5) disposed below the heat exchanger and above an upper end of a reactor core (13) placed in a reactor pressure vessel (15); a non-condensate gas discharge line (8) connected at a first end thereof to an upper section of the condensate storage tank (5) and at a second end thereof to a suppression pool (20); a second condensate discharge line (9) connected at a first end thereof to a position below that section of the condensate storage tank (5) to which the first end of the non-condensate gas discharge line (8) is connected, and at a second end thereof to the suppression pool (20); and a condensate return line (10) connected at a first end thereof to a position below that section of the condensate storage tank (5) to which the first end of the second condensate discharge line (9) is connected, and at a second end thereof to a side portion of the reactor pressure vessel (15), the side portion being above the upper end of the core (13).

    摘要翻译： 公开了一种被动的残余散热系统和核动力装置设备，其构造成即使发生反应堆压力容器（15）的流体管线断裂，并且由于任何原因，减轻主要容纳容器（17）的内部压力的升高， 向反应堆压力容器（15）供应冷却剂（2）失败。 本发明包括：设置在高于主要容纳容器（17）的位置处的热交换器（1）; 设置在所述热交换器的下方和放置在反应堆压力容器（15）内的反应堆芯（13）的上端上方的冷凝水储存箱（5）。 一个非冷凝气体排放管线（8），其第一端连接到冷凝水储存箱（5）的上部，第二端连接到一个抑制池（20）; 第二冷凝物排出管线（9），其在其第一端连接到所述冷凝水罐（5）的所述非冷凝气体排出管线（8）的第一端所连接的所述部分下方的位置，并且在 第二端到达抑制池（20）; 以及冷凝水返回管线（10），其在其第一端连接到第二冷凝物排出管线（9）的第一端连接到的冷凝水储存罐（5）的该部分下方的位置，并且在第二端 在所述反应堆压力容器（15）的侧部，所述侧部位于所述芯（13）的上端之上。

    KERNTECHNISCHE ANLAGE
    66.
    发明公开
    KERNTECHNISCHE ANLAGE 有权
    核电厂

    公开(公告)号：EP2700074A1

    公开(公告)日：2014-02-26

    申请号：EP12717272.4

    申请日：2012-04-23

    申请人： Siempelkamp Nukleartechnik GmbH

    发明人： KUPKE, Peter ,  KLUTE, Stefan ,  THOMAS, Andreas

    IPC分类号： G21C9/00 ,  G21C11/00 ,  G21C19/07 ,  G21D1/00 ,  G21F7/00

    CPC分类号： G21C9/00 ,  G21C11/00 ,  G21C19/07 ,  G21D1/00 ,  G21F7/00 ,  Y02E30/40

    摘要： The invention relates to a nuclear plant, in particular a nuclear reactor plant or reprocessing plant, comprising a building (1) and a spent fuel pool (6) arranged inside the building (1) below a building floor (2), in which spent fuel pool fuel elements are stored. Said plant is characterized in that a protective hood (7) that spans the spent fuel pool (6) is arranged below the building floor (2) and above the spent fuel pool (6), which protective hood protects the spent fuel pool (6) and the fuel elements stored therein from falling debris, in particular building debris, in the event of damage to the building (1).

    EMERGENCY CORE COOLING SYSTEMS FOR PRESSURIZED WATER REACTOR
    67.
    发明公开
    EMERGENCY CORE COOLING SYSTEMS FOR PRESSURIZED WATER REACTOR 有权
    应急堆芯冷却系统用于加压水反应堆

    公开(公告)号：EP2689426A1

    公开(公告)日：2014-01-29

    申请号：EP12760848.7

    申请日：2012-03-22

    申请人： Babcock & Wilcox Nuclear Energy, Inc.

    发明人： MALLOY, John, D.

    IPC分类号： G21C9/00

    CPC分类号： G21C15/18 ,  G21C1/32 ,  G21C9/012 ,  G21C9/033 ,  G21D3/06 ,  Y02E30/32

    摘要： A pressurized water nuclear reactor (PWR) has an internal pressurizer volume containing a steam bubble and is surrounded by a containment structure. A condenser is disposed inside the containment structure and is operatively connected with an external heat sink disposed outside of the containment structure. A valve assembly operatively connects the PWR with the condenser responsive to an abnormal operation signal such that the condenser condenses steam from the steam bubble while rejecting heat to the external heat sink and returns the condensed water to the PWR. A quench tank contains water with dissolved neutron poison. A valved tank pressurizing path selectively connects the steam bubble to the quench tank to pressurize the quench tank, and a valved soluble poison delivery path selectively connects the quench tank to the PWR such that the quench tank under pressure from the steam bubble discharges water with dissolved neutron poison into the PWR.