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    Fast Neutron Reactor and Neutron Reflector Block of a Fast Neutron Reactor
    2.
    发明申请
    Fast Neutron Reactor and Neutron Reflector Block of a Fast Neutron Reactor 审中-公开
    快中子反应堆快中子反应堆和中子反射块

    公开(公告)号：US20170018320A1

    公开(公告)日：2017-01-19

    申请号：US15102445

    申请日：2014-12-08

    Applicant: Joint Stock Company "AKME-Engineering"

    Inventor： Sergey Viktorovich Bulavkin

    IPC: G21C15/10 ,  G21C11/06 ,  G21C15/28 ,  G21C1/02

    CPC classification number: G21C15/10 ,  G21C1/02 ,  G21C11/06 ,  G21C15/28 ,  Y02E30/34 ,  Y02E30/35

    Abstract: The invention relates to the field of nuclear engineering, and more particularly to designs for removable neutron reflector blocks for heavy liquid metal-cooled fast neutron reactors. The present fast neutron reactor contains a core consisting of heavy liquid metal-cooled fuel rods, and neutron reflector blocks, disposed around the core, which comprise a steel casing with at least one inlet opening in the side walls thereof above the core boundary, said inlet opening being intended for diverting part of the coolant flow from the space between the blocks into the casing, and at least one vertical pipe mounted in the casing, through which the diverted coolant flow, which has passed through the upper and lower boundaries of the core, enters the bottom part of the casing; also, on the outer side of the casing, above the inlet opening, there is mounted a throttling device for creating hydraulic resistance to the coolant flow in the space between the blocks. The technical result is an increase in the operating safety and the performance of a fast neutron reactor and a reduction in the heat exchange surface of the steam generator.

    Abstract translation: 本发明涉及核工程领域，更具体地涉及用于重液态金属冷却快中子反应堆的可移除中子反射块的设计。 本发明的快中子反应堆包含由重液态金属冷却的燃料棒组成的核心和设置在芯体周围的中子反射器块，该中子反射块包括一个在壳体边界上方的侧壁中具有至少一个入口的钢壳体， 入口开口旨在将冷却剂流的一部分从块之间的空间转移到壳体中，以及安装在壳体中的至少一个垂直管，通过该垂直管已经通过了转向冷却剂流的上部和下部边界 芯，进入套管的底部; 另外，在外壳的外侧，在入口开口的上方，安装有用于在块之间的空间中产生对冷却剂流的液压阻力的节流装置。 技术结果是增加了快中子反应器的运行安全性和性能，并减少了蒸汽发生器的热交换面。

    Method of cooling the ceiling reflector in a nuclear reactor
    4.
    发明授权
    Method of cooling the ceiling reflector in a nuclear reactor 失效
    在核反应堆中冷却吸顶反射器的方法

    公开(公告)号：US4066499A

    公开(公告)日：1978-01-03

    申请号：US680140

    申请日：1976-04-26

    Applicant: Hans-Peter Buthmann

    Inventor： Hans-Peter Buthmann

    IPC: G21C1/12 ,  G21C1/24 ,  G21C15/10 ,  G21C15/12 ,  G21C15/18 ,  G21C9/00

    CPC classification number: G21C15/10 ,  G21C15/18 ,  Y02E30/33

    Abstract: In a gas-cooled solid-moderated high-temperature reactor where fuel elements are introduced into the core through feed pipes in the ceiling reflector, the ceiling is cooled after reactor shutdown by introducing cooled gas through centrally arranged feed pipes and by removing the gas through the other feed pipes located radially outwardly of the inlet feed pipes. This arrangement effects a flow of the gas generally radially outwardly over the ceiling reflector. After the gas is removed from the core it is circulated through a closed circuit, cooled and blown back through the inlet feed pipes into the core.

    5.
    发明授权
    失效

    公开(公告)号：UST927001I4

    公开(公告)日：1974-10-01

    申请号：US927001D

    申请日：1973-03-30

    IPC: G21C15/10

    CPC classification number: G21C15/10 ,  Y02E30/40

    SYSTEMS AND METHODS TO ENHANCE PASSIVE CONTAINMENT COOLING SYSTEM
    8.
    发明申请
    SYSTEMS AND METHODS TO ENHANCE PASSIVE CONTAINMENT COOLING SYSTEM 失效
    加强被动冷却系统和方法

    公开(公告)号：US20030048865A1

    公开(公告)日：2003-03-13

    申请号：US09781455

    申请日：2001-02-12

    Inventor： Yee Kwong Cheung ,  Robert E. Gamble ,  Atambir Singh Rao

    IPC: G21C009/00

    CPC classification number: G21C15/10 ,  G21C9/012 ,  Y02E30/40

    Abstract: A nuclear reactor containment cooling system includes a containment vessel having a drywell and a wetwell, a cooling condenser submerged in a cooling pool of water located outside the containment vessel, a vent line extending from the condenser to a suppression pool disposed in the wetwell, and at least one drain line extending from the condenser to a condensate drain tank located in the drywell. An end of the drain line is vertically submerged below the surface of a pool of water in the drain tank. To enhance flow, a blower can be located in the drain line. The containment cooling system can include a drywell gas recirculation subsystem coupled to the vent line, and including a suction pipe coupled to the vent line, at least one valve located in the suction pipe, at least one blower coupled to the suction line, and a discharge pipe in flow communication with the drywell.

    Abstract translation: 核反应堆容纳冷却系统包括具有干井和水槽的容纳容器，浸没在位于容纳容器外部的水的冷却池中的冷却冷凝器，从冷凝器延伸到设置在水槽中的抑制池的排气管线，以及 至少一个从冷凝器延伸到位于干井内的冷凝水排放箱的排水管线。 排水管的一端垂直淹没在排水槽内的水池表面下方。 为了提高流量，鼓风机可以位于排水管路中。 容纳冷却系统可以包括耦合到排气管线的干井气体再循环子系统，并且包括联接到排气管线的抽吸管，位于吸入管中的至少一个阀，耦合到吸入管线的至少一个鼓风机，以及 排水管与干井流通。

    High-temperature reactor
    9.
    发明授权
    High-temperature reactor 失效
    高温反应釜

    公开(公告)号：US4795607A

    公开(公告)日：1989-01-03

    申请号：US43844

    申请日：1987-04-29

    Applicant: Herbert Reutler ,  Gunter Lohnert ,  Johannes Lukaszewicz

    Inventor： Herbert Reutler ,  Gunter Lohnert ,  Johannes Lukaszewicz

    IPC: G21C1/12 ,  G21C1/07 ,  G21C15/10 ,  G21C9/00 ,  G21C15/18

    CPC classification number: G21C1/07 ,  G21C15/10 ,  Y02E30/33 ,  Y02E30/36 ,  Y10S376/908 ,  Y10S376/911

    Abstract: Gas-cooled high-temperature nuclear reactor having a reactor core comprising individual fuel elements provided with means for forming a barrier against the release of fission products producible therein during reactor operation, the fuel elements being received in a cylindrical barrel formed of an inner graphite layer functioning as a reflector, an outer layer of insulating material surrounding the inner layer, and a metallic receptacle, the inner and outer layers and the receptacle being formed of respective side, bottom and cover portions, the side and cover portions of the inner layer being formed with first channels into which means for controlling the reactors are insertable, the bottom, side and cover portions of the inner layer being further formed with second channels wherein, during reactor operation, cooling gas is circulated under pressure from the bottom to the top of the receptacle, the bottom portion of the inner layer having first openings for introducing cooling gas into the second channels during reactor operation and second openings for withdrawing during reactor operation cooling gas heated by passage through the reactor core; the inner and outer layers and the cylindrical core barrel having a heat conductivity and a thermal capacity and the reactor core having such a size, shape, power density and moderation ratio that a first temperature at which the core becomes subcritical for all possible accident conditions is below a second temperature at which the barrier means are destroyed, and, when loss of pressure of the cooling gas is experienced, after-heat generated in the core being removable by heat conduction and radiation through the inner and outer layers and the core barrel to a heat sink located outside the receptacle, in such a way that the fuel elements remain at a temperature below the second temperature.

    Abstract translation: 气体冷却的高温核反应堆具有反应堆堆芯，该反应堆堆芯包括单独的燃料元件，该燃料元件设置有用于在反应堆操作期间形成阻挡其中可生产的裂变产物的阻挡的装置，燃料元件被容纳在由内部石墨层 用作反射器，围绕内层的绝缘材料的外层和金属容器，内层和外层以及容器由相应的侧面，底部和盖部分形成，内层的侧面和封面部分是 形成有第一通道，用于控制反应器的装置可插入其中，内层的底部，侧部和盖部分进一步形成有第二通道，其中在反应器操作期间，冷却气体在压力下从底部到顶部循环 所述容器，所述内层的底部具有用于引入冷却气体int的第一开口 o在反应堆操作期间的第二通道和用于在反应器操作期间抽出的第二开口通过反应堆堆芯加热的冷却气体; 所述内层和外层和所述圆柱形芯筒具有导热性和热容量，并且所述反应堆芯具有这样的尺寸，形状，功率密度和调节比，使得在所有可能的事故条件下所述芯变为亚临界的第一温度为 低于阻挡装置被破坏的第二温度，并且当经历冷却气体的压力损失时，在芯体中产生的后热可以通过内外层和核心筒的热传导和辐射而被除去， 位于容器外部的散热器，使得燃料元件保持在低于第二温度的温度。

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