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    LOSS-OF-COOLANT ACCIDENT REACTOR COOLING SYSTEM
    3.
    发明申请
    LOSS-OF-COOLANT ACCIDENT REACTOR COOLING SYSTEM 审中-公开
    冷却故障反应器冷却系统

    公开(公告)号：US20140321597A1

    公开(公告)日：2014-10-30

    申请号：US14289545

    申请日：2014-05-28

    申请人： SMR Inventec, LLC

    发明人： Krishna P. SINGH ,  Joseph RAJKUMAR

    IPC分类号： G21C15/18

    CPC分类号： G21C15/18 ,  G21C9/004 ,  G21C13/02 ,  G21C15/12 ,  G21D1/00 ,  G21D1/006 ,  Y02E30/40

    摘要： A nuclear reactor cooling system with passive cooling capabilities operable during a loss-of-coolant accident (LOCA) without available electric power. The system includes a reactor vessel with nuclear fuel core located in a reactor well. An in-containment water storage tank is fluidly coupled to the reactor well and holds an inventory of cooling water. During a LOCA event, the tank floods the reactor well with water. Eventually, the water heated by decay heat from the reactor vaporizes producing steam. The steam flows to an in-containment heat exchanger and condenses. The condensate is returned to the reactor well in a closed flow loop system in which flow may circulate solely via gravity from changes in phase and density of the water. In one embodiment, the heat exchanger may be an array of heat dissipater ducts mounted on the wall of the inner containment vessel surrounded by a heat sink.

    摘要翻译： 具有被动冷却功能的核反应堆冷却系统，可在冷却液事故损失（LOCA）下运行，无需电力。 该系统包括具有位于反应器井中的核燃料芯的反应器容器。 一个内置储水罐与反应器井流体耦合并保存冷却水的库存。 在LOCA事件期间，坦克用水充满水。 最终，通过来自反应器的衰变热加热的水蒸发产生蒸汽。 蒸汽流入容纳式热交换器并冷凝。 冷凝物在封闭的流动回路系统中返回到反应器，其中流动可以通过重力从水的相位和密度的变化中循环。 在一个实施例中，热交换器可以是安装在由散热器包围的内部容纳容器的壁上的散热器管道的阵列。

    PASSIVE REACTOR COOLING SYSTEM
    4.
    发明申请
    PASSIVE REACTOR COOLING SYSTEM 有权
    被动式反应器冷却系统

    公开(公告)号：US20140321596A1

    公开(公告)日：2014-10-30

    申请号：US14289525

    申请日：2014-05-28

    申请人： SMR Inventec, LLC

    发明人： Krishna P. SINGH ,  Joseph RAJKUMAR

    IPC分类号： G21C15/18

    CPC分类号： G21C15/18 ,  G21C9/004 ,  G21C13/02 ,  G21C15/12 ,  G21D1/00 ,  G21D1/006 ,  G21Y2002/207 ,  G21Y2004/302 ,  Y02E30/40

    摘要： A nuclear reactor cooling system with passive cooling capabilities operable during a reactor shutdown event without available electric power. In one embodiment, the system includes a reactor vessel with nuclear fuel core and a steam generator fluidly coupled thereto. Primary coolant circulates in a flow loop between the reactor vessel and steam generator to heat secondary coolant in the steam generator producing steam. The steam flows to a heat exchanger containing an inventory of cooling water in which a submerged tube bundle is immersed. The steam is condensed in the heat exchanger and returned to the steam generator forming a closed flow loop in which the secondary coolant flow is driven by natural gravity via changes in density from the heating and cooling cycles. In other embodiments, the cooling system is configured to extract and cool the primary coolant directly using the submerged tube bundle heat exchanger.

    摘要翻译： 具有被动冷却能力的核反应堆冷却系统在反应堆关闭事件期间可操作而无可用电力。 在一个实施例中，系统包括具有核燃料芯的反应器容器和与其流体耦合的蒸汽发生器。 主冷却剂在反应堆容器和蒸汽发生器之间的流动回路中循环，以在蒸汽发生器中加热产生蒸汽的二次冷却剂。 蒸汽流入含有浸没浸没管束的冷却水库存的热交换器。 蒸汽在热交换器中冷凝并返回到蒸汽发生器，形成闭合的流动回路，其中二次冷却剂流由自然重力通过来自加热和冷却循环的密度变化来驱动。 在其他实施例中，冷却系统构造成使用浸没式管束热交换器直接提取和冷却一次冷却剂。