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    Single fluid molten salt nuclear breeder reactor
    1.
    发明授权
    Single fluid molten salt nuclear breeder reactor 失效
    单流体乳酸盐核酸反应器

    公开(公告)号：US3743577A

    公开(公告)日：1973-07-03

    申请号：US3743577D

    申请日：1968-06-03

    Applicant: ATOMIC ENERGY COMMISSION

    Inventor： PERRY A ,  SMITH O ,  BETTIS E ,  MACPHERSON H

    IPC: G21C1/16 ,  G21C1/22 ,  G21C3/54 ,  G21C5/20

    CPC classification number: G21C1/22 ,  G21C3/54 ,  G21C5/20 ,  G21Y2002/30 ,  G21Y2004/30 ,  Y02E30/38

    Abstract: A MOLTEN-SALT-FUELED GRAPHITE-MODERATED NUCLEAR BREEDER REACTOR CHARACTERIZED BY A SINGLE SALT MIXTURE CONTAINING BOTH FISSILE AND FERTILE MATERIAL WHICH SERVES AS BOTH FUEL AND BLANKET FLUID. THE REACTOR IS DIVIDED INTO CORE AND THE BLANKET REGIONS WHICH ARE DISTINGUISHED BY THE DEGREE OF NEUTRON MODERATION PROVIDED THEREIN. THE DEGREE OF NEUTRON MODERATION IN THE CORE AND BLANKET REGIONS MAY BE VARIED BY VARYING THE VOLUME FRACTION OF SALT MIXTURE PRESENT IN THE EACH REGION, BY VARYING THE DENSITY OF THE GRAPHITE MODERATOR IN EACH REGION, OR BY A COMBINATION OF THE TWO METHODS. THE COMPOSITION OF THE SALT MIXTURE AND THE NEUTRON MODERATION PROVIDED IN EACH REGION ARE SELECTED SO THAT NEUTRON ADSORPTION BY THE FISSILE MATERIAL PREDOMINATES IN THE CORE AND ABSORPTION OF NEUTRONS BY THE FERTILE MATERIAL PREDOMINATES IN THE BLANKET REGION.

    Hydraulic control rod drive system
    2.
    发明授权
    Hydraulic control rod drive system 失效
    液压控制驱动系统

    公开(公告)号：US3573166A

    公开(公告)日：1971-03-30

    申请号：US3573166D

    申请日：1968-07-24

    Applicant: ATOMIC ENERGY COMMISSION

    Inventor： GERMER JOHN H

    IPC: G21C7/16 ,  G21C1/16

    CPC classification number: G21C7/16 ,  G21Y2002/201 ,  G21Y2004/30 ,  Y02E30/31 ,  Y02E30/34 ,  Y02E30/39

    Abstract: A SYSTEM FOR CONTROLLING A NUCLEAR REACTOR UTILIZING PRESSUREIZED COOLANT FOR RAISING CONTROL RODS OUT OF THE REACTOR CORE. THE SYSTEM POSITIONS INDIVIDUAL CONTROL RODS OR GROUPS THEREOF IN EITHER AN ALL-IN OR AN ALL-OUT POSITION, AND INCORPORATES MEANS FOR ASSURING FAIL-SAFE OPERATION AND FOR POSITION INDICATION OF THE RODS. THE SIMPLICITY OF THE SYSTEM MAKES IT FEASIBLE TO PROVIDE A SUFFICIENT NUMBER OF WEAK CONTROL RODS TO PERMIT ALL-IN OR ALL-OUT OPERATION WITHOUT EXCESSIVE INCREMENTS OF REACTIVITY. THE INDIVIDUAL CONTROL RODS IN LARGE THERMAL REACTORS, FOR EXAMPLE MAY BE OPERATED IN GROUPS WIDELY DISPERSED THROUGHOUT THE CORE, SUFFICIENTLY SPACED THAT THE RODS HAVE LITTLE OR NO INTERACTION; WHILE A FAST REACTOR IS MUCH MORE CLOSELY-COUPLED. WHILE THIS SYSTEM IS PARTICULARLY APPLICABLE TO SODIUM-COOLED FAST REACTORS, IT CAN BE ADAPTED TO OTHER TYPES OF REACTORS.

    Molten salt reactor core with reflector
    5.
    发明授权
    Molten salt reactor core with reflector 有权

    公开(公告)号：US10276269B2

    公开(公告)日：2019-04-30

    申请号：US15610182

    申请日：2017-05-31

    Applicant: M. Sheldon Hansen

    Inventor： M. Sheldon Hansen

    IPC: G21C1/16 ,  G21C1/22 ,  G21C3/10 ,  G21C3/32 ,  G21C3/54 ,  G21C5/02 ,  G21C5/12 ,  G21C7/00 ,  G21D9/00 ,  G21C11/06 ,  G21C19/14 ,  G21C19/19 ,  G21C3/336

    Abstract: While the described systems can include any suitable component, in some cases, they include a graphite reactor core defining an internal space that, in some cases, houses one or more fuel wedges, where each wedge defines one or more fuel channels that extend from a first end to a second end of the wedge. In some cases, one or more of the fuel wedges comprise multiple wedge sections that are coupled together end to end and/or in any other suitable manner. In some cases, one or more alignment pins also extend between two sections of a fuel wedge to align the sections. In some cases, one or more seals are also disposed between two sections of a fuel wedge. Thus, in some cases, the reactor core can be relatively long (e.g., to be a pipeline reactor). In some cases, the reactor core is also disposed within a graphite reflector. Other implementations are described.

    NUCLEAR REACTOR
    6.
    发明申请
    NUCLEAR REACTOR 审中-公开
    核反应堆

    公开(公告)号：US20090207963A1

    公开(公告)日：2009-08-20

    申请号：US12301562

    申请日：2007-05-16

    Applicant: Gerrit Clemens Van Uitert

    Inventor： Gerrit Clemens Van Uitert

    IPC: G21C1/16 ,  G21C11/06 ,  G21C11/08

    CPC classification number: G21C1/32 ,  G21C9/00 ,  G21C11/08 ,  G21C15/28 ,  Y02E30/40

    Abstract: The present invention generally relates to a nuclear reactor, comprising a reactor core, neutron reflectors surrounding the core on all sides, uranium oxide as reactor fuel and a coolant that is liquid at proces conditions and solid at room temperature. The invention is characterized in that the nuclear reactor comprises a thermal isolation which is impermeable for the coolant, which is of a different material than the coolant and which has a melting point higher than the temperature in the reactor, in such a way that the thermal isolation is surrounding the reactor core and the neutron reflectors on all sides in order to provide a leak-tight containment function. Therefore the phenomenon is being used that the temperature on the outside of the installation is always far below the melting point of the coolant, in such a way that the coolant solidifies on the outside of the installation under all possible circumstances. The heating channels, which are preferably embedded in the reflectors, contain heating elements for heating the reactor core to a temperature higher than the melting point of the coolant before the reactor is filled with the coolant and before the start up of the reactor begins. The whole primary system of the installation may fit in a transportable container.

    Abstract translation: 本发明一般涉及一种核反应堆，其包括反应堆堆芯，围绕所有侧面的核心的中子反射器，作为反应堆燃料的氧化铀和在室温条件下为液态的冷却剂和在室温下为固体的冷却剂。 本发明的特征在于，核反应堆包括对于冷却剂是不可渗透的热隔离，所述冷却剂是与冷却剂不同的材料，其熔点高于反应器中的温度，使得热 隔离是围绕反应堆核心和中子反射器在所有方面，以提供一个密封的封闭功能。 因此，正在使用这样的现象，即，在所有可能的情况下，设备外部的温度总是远低于冷却剂的熔点，使得冷却剂在设备的外部固化。 优选地嵌入反射器中的加热通道包含用于在反应器填充冷却剂之前并且在反应器启动开始之前将反应堆芯体加热至高于冷却剂熔点的温度的加热元件。 安装的整个主要系统可以装在可运输的容器中。

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