INTRINSICALLY SAFE NUCLEAR REACTOR
    4.
    发明申请
    INTRINSICALLY SAFE NUCLEAR REACTOR 审中-公开
    本质安全核反应堆

    公开(公告)号:US20160125963A1

    公开(公告)日:2016-05-05

    申请号:US14527356

    申请日:2014-10-29

    CPC classification number: G21C1/02 G21C9/027 G21C15/247 Y02E30/34 Y02E30/35

    Abstract: An improved nuclear fission reactor of the liquid metal cooled type including a core configuration allowing for only two operational states, “Power” or “Rest”. The flow of the primary cooling fluid suspends the core in the “Power” state, with sufficient flow to remove the heat to an intermediate heat exchanger during normal operation. This invention utilizes the force of gravity to shut down the reactor after any loss of coolant flow, either a controlled reactor shut down or a “LOCA” event, as the core is controlled via dispersion of fuel elements. Electromagnetic pumps incorporating automatic safety electrical cut-offs are employed to shutdown the primary cooling system to disassemble the core to the “Rest” configuration due to a loss of secondary coolant or loss of ultimate heat sink. This invention is a hybrid pool-loop pressurized high-temperature or unpressurized reactor unique in its use of a minimum number of components, utilizing no moving mechanical parts, no rotating seals, optimized piping, and no control rods. Thus defining an elegantly simple intrinsically safe nuclear reactor.

    Abstract translation: 一种改进的液态金属冷却型核裂变反应堆,其包括允许只有两个操作状态“电源”或“休息”的核心配置。 主冷却流体的流动使芯处于“动力”状态,具有足够的流动以在正常操作期间将热量移除到中间热交换器。 本发明利用重力来在冷却剂流动的任何损失(受控反应堆关闭或“LOCA”)事件之后关闭反应器,因为通过燃料元件的分散来控制核心。 采用包含自动安全电气截止阀的电磁泵关闭主冷却系统,由于二次冷却液的损失或最终的散热器损失,将芯拆卸到“休息”配置。 本发明是混合池循环加压高温或非加压反应器,其独特的是使用最少数量的部件,不使用移动的机械部件,没有旋转密封件,优化的管道和没有控制棒。 从而确定了一个优雅简单的本质安全的核反应堆。

    Nuclear Reactor with Liquid Metal Coolant
    5.
    发明申请
    Nuclear Reactor with Liquid Metal Coolant 有权
    具有液态金属冷却液的核反应堆

    公开(公告)号:US20150294745A1

    公开(公告)日:2015-10-15

    申请号:US14646503

    申请日:2012-11-26

    CPC classification number: G21C1/03 G21C15/247 G21D1/006 Y02E30/34 Y02E30/35

    Abstract: A nuclear reactor with a liquid metal coolant includes a housing having a separating shell disposed therein. In the annular space between the housing and the separating shell are disposed at least one steam generator and at least one pump. Inside the separating shell there is an active region, above which a heat collector is disposed in communication with the vertically central portion of the steam generator in order to separate a stream of liquid metal coolant into ascending and descending flows, or the heat collector is in communication with the upper portion of the steam generator in order to create a counter-flow heat exchange regime. Below the reactor head is an upper horizontal cold collector with an unfilled level of coolant, and below the steam generator is a lower accumulating collector in communication with the upper cold collector.

    Abstract translation: 具有液态金属冷却剂的核反应堆包括其中设置有分离壳体的壳体。 在壳体和分离壳体之间的环形空间中设置有至少一个蒸汽发生器和至少一个泵。 在分离壳内部有一个活动区域,在该区域上方,与蒸汽发生器的垂直中心部分相连接设置集热器,以将液态金属冷却剂流分离成上升和下降的流动,或者集热器处于 与蒸汽发生器的上部连通以产生逆流热交换方案。 在反应器头下方是具有未填充水平的冷却剂的上部水平冷凝器,并且在蒸汽发生器下方是与上部冷收集器连通的下部累积集水器。

    SFR NUCLEAR REACTOR OF THE INTEGRATED TYPE WITH IMPROVED COMPACTNESS AND CONVECTION
    9.
    发明申请
    SFR NUCLEAR REACTOR OF THE INTEGRATED TYPE WITH IMPROVED COMPACTNESS AND CONVECTION 审中-公开
    集成型SFR核反应堆具有改进的紧凑性和对流性

    公开(公告)号:US20110222642A1

    公开(公告)日:2011-09-15

    申请号:US13129485

    申请日:2009-10-12

    Abstract: The invention relates to a novel architecture for a nuclear reactor of the integrated type.The invention comprises:realising the hot area and cold area separation device for the primary sodium flow in the form of two walls with cuts,providing two pumping groups hydraulically in series, one for the flow of sodium from the hot area to the cold area through the intermediate exchangers and the other in the cold area;providing outlet windows of the intermediate exchangers below the lower wall;providing outlet windows of the removal exchangers of the decay heat above the cold area, wherein all of clearances between the walls with cuts and the heat removal exchangers and the height between the two walls with cuts are previously determined so as to, during normal operation, take up differential movements between the walls, exchangers and vessel and to make it possible to establish during normal operation a thermal stratification of the primary sodium in the space defined between the horizontal portions of the two walls and so as to reduce, in case of an unexpected stop of a single pumping group, the mechanical stress applied to the walls and due to the portion of the primary sodium flow passing between said clearances.

    Abstract translation: 本发明涉及一体化型核反应堆的新型结构。 本发明包括:实现用于具有切割的两壁形式的主要钠流的热区域和冷区域分离装置,提供两个串联的液压组,一个用于从热区域到冷区域的钠流 中间交换器,另一个在寒冷地区; 在下壁下方设置中间交换器的出口窗口; 提供在冷区域之上的腐蚀热的去除交换器的出口窗口,其中预先确定具有切口的壁和除热交换器之间的所有间隙以及具有切口的两个壁之间的高度,以便在正常操作期间, 吸收壁,交换器和容器之间的差异运动,并且使得可以在正常操作期间建立在两个壁的水平部分之间限定的空间中的主要钠的热分层,以便在 单个泵送组的意外停止,施加到壁上的机械应力以及由于在所述间隙之间通过的初级钠流的部分。

    FAST BREEDER REACTOR TYPE NUCLEAR POWER PLANT SYSTEM
    10.
    发明申请
    FAST BREEDER REACTOR TYPE NUCLEAR POWER PLANT SYSTEM 审中-公开
    快速反应堆型核电厂系统

    公开(公告)号:US20090122944A1

    公开(公告)日:2009-05-14

    申请号:US12190795

    申请日:2008-08-13

    CPC classification number: G21C1/02 F16L43/003 G21C15/247 Y02E30/34

    Abstract: A fast breeder reactor type nuclear power plant system including a reactor vessel provided with a core and a pipe of primary loop coolant for supplying primary loop coolant to the reactor vessel.One or more bending parts are formed on at least the pipe of primary loop coolant of the pipes, and a part of the bending part on a downstream side is provided with a flow path having a non-circular sectional configuration wherein the negative side of the bending part is formed in either a planar or flat shape.

    Abstract translation: 一种快速增殖反应堆型核电站系统,其包括设置有核心的反应堆容器和用于将一次循环冷却剂供应到反应堆容器的主回路冷却剂管。 一个或多个弯曲部分形成在至少管道的一次回路冷却剂的管道上,并且下游侧的弯曲部分的一部分设置有具有非圆形截面构造的流路,其中, 弯曲部分形成为平面或扁平形状。

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