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    Nuclear reactor system with lift-out core assembly
    1.
    发明授权
    Nuclear reactor system with lift-out core assembly 有权

    公开(公告)号：US11610694B2

    公开(公告)日：2023-03-21

    申请号：US17398762

    申请日：2021-08-10

    申请人： Radiant Industries, Incorporated

    发明人： Doug Bernauer ,  Armand Eliassen

    IPC分类号： G21C3/33 ,  G21C19/10 ,  G21C19/18 ,  G21C1/12 ,  G21C5/10 ,  G21C19/20 ,  G21C19/06

    摘要： A modular nuclear reactor system includes a lift-out, replaceable nuclear reactor core configured for replacement as a singular unit during a single lift-out event, such as rather than lifting and replacing individual fuel assemblies and/or fuel elements. The system includes a reactor vessel and a power generation system configured to convert thermal energy in a high temperature working fluid received from the reactor vessel into electrical energy. The reactor vessel includes: a vessel inlet and an adjacent vessel outlet arranged near a bottom on the vessel; a vessel receptacle configured to receive a unified core assembly; locating datums in the base of the vessel receptacle and configured to constrain a core assembly in multiple degrees of freedom; and an interstitial zone surrounding the vessel receptacle and housing a set of control or moderating drums.

    Destruction of plutonium
    2.
    发明授权
    Destruction of plutonium 失效
    钚破坏

    公开(公告)号：US5513226A

    公开(公告)日：1996-04-30

    申请号：US248319

    申请日：1994-05-23

    申请人： Alan M. Baxter ,  Richard K. Lane

    发明人： Alan M. Baxter ,  Richard K. Lane

    IPC分类号： G21C1/12 ,  G21C1/30 ,  G21C3/04 ,  G21C3/28 ,  G21C7/00 ,  G21C7/04 ,  G21G1/08

    CPC分类号： G21C1/30 ,  G21C1/12 ,  G21C1/306 ,  G21C3/042 ,  G21C3/28 ,  G21C7/00 ,  G21C7/04 ,  G21Y2002/201 ,  G21Y2002/60 ,  G21Y2002/601 ,  G21Y2004/20 ,  G21Y2004/60 ,  Y02E30/33 ,  Y02E30/37 ,  Y10S376/901

    摘要： Plutonium is effectively and economically rendered unsuitable for employment in a device for creating a nuclear detonation. Weapons-grade plutonium is made into ceramic fuel in the form of spheroids of submillimeter size, coated with multi-layer fission-product-retentive coatings and disposed in sealed fuel chambers in graphite block fuel elements. These elements are used to form a core for a modular helium-cooled high temperature nuclear reactor which is operated to efficiently generate power by causing the hot high pressure helium coolant to drive a gas turbine directly connected to an electrical generator, which nuclear fuel core has about a 3-year lifetime. Spent nuclear fuel elements are removed at the end of 3 years and shifted to form the core for an accelerator-driven helium-cooled reactor wherein a subcritical core of spent fuel elements is safely caused to effectively continuously fission by a neutron flux created by a Linac which bombards a lead target with a beam of high energy protons. At the end of 1 to 2 more years, more than 99% of the original Pu-239 has fissioned or been transmuted, and the isotope distribution of remaining plutonium renders it no longer useful for carrying out a nuclear detonation. Such fuel elements can be securely stored without reprocessing in simple metal canisters in a long-term repository.

    摘要翻译： 钚在有效和经济上不适合用于创造核爆炸装置的工作。 武器级钚制成陶瓷燃料，其形式为亚毫米尺寸的球体，涂覆有多层裂变产物保持性涂层，并设置在石墨块燃料元件的密封燃料室中。 这些元件用于形成用于模块化氦冷却的高温核反应堆的核心，其通过使热高压氦冷却剂驱动直接连接到发电机的燃气轮机而被操作以有效地发电，该核燃料芯具有 大约3年的一生。 消耗的核燃料元件在3年结束时被去除，并转移到形成用于加速器驱动的氦冷却反应器的核心，其中乏燃料元素的亚临界核心被安全地引起由线性加速器产生的中子通量有效地连续裂变 它用一束高能质子轰击了一个铅靶。 在1至2年的最后，原始Pu-239的99％以上已经分裂或转变，剩余钚的同位素分布使其不再适用于进行核爆炸。 这种燃料元件可以安全地存储，而不需要在长期储存库中的简单金属罐中进行再处理。

    Gas cooled high temperature reactor charged with spherical fuel elements
    3.
    发明授权
    Gas cooled high temperature reactor charged with spherical fuel elements 失效
    装有球形燃料元件的气冷高温反应器

    公开(公告)号：US4778646A

    公开(公告)日：1988-10-18

    申请号：US760414

    申请日：1985-07-30

    申请人： Claus Elter ,  Jurgen Rautenberg ,  Josef Schoening ,  Wilfried Stracke

    发明人： Claus Elter ,  Jurgen Rautenberg ,  Josef Schoening ,  Wilfried Stracke

    IPC分类号： G21C1/12 ,  G21C1/07 ,  G21C1/24 ,  G21C19/20 ,  G21C19/28

    CPC分类号： G21C19/207 ,  G21C1/07 ,  Y02E30/36

    摘要： The invention relates to a gas cooled high temperature reactor located in the cavity of a pressure vessel, with spherical fuel elements, and removal apparatus for fuel elements. The latter is made of at least one ceramic pebble outlet tube extending through the graphite structural parts of the nuclear reactor (bottom reflector, bottom layers) and a number of metal pebble outlet tubes installed through the bottom of the pressure vessel. They are arranged coaxially in the liner of the passage through the vessel. To be able to dismantle the metal pebble outlet tubes, they are constructed of several releasably interconnected tube segments. Between the uppermost tube segment and the corresponding ceramic pebble outlet tube a compensating tube is provided and connected with the tube segment by means of a sliding joint. The other end of the compensating tube is fastened to the thermal bottom shield. Relative movements caused by the thermal expansion of the bottom shield and the pebble outlet tubes are compensated by the slide joints. Simultaneously, the necessary tight sealing is assured.

    摘要翻译： 本发明涉及一种位于压力容器空腔中的气体冷却式高温反应器，其具有球形燃料元件和用于燃料元件的去除装置。 后者由延伸穿过核反应堆（底部反射器，底层）的石墨结构部分和穿过压力容器底部安装的多个金属卵石出口管的至少一个陶瓷卵石出口管制成。 它们同轴地布置在通过容器的通道的衬里中。 为了能够拆卸金属卵石出口管，它们由几个可释放地连接的管段构成。 在最上管段和相应的陶瓷卵石出口管之间，通过滑动接头提供并与管段连接的补偿管。 补偿管的另一端固定在热底盖上。 由底板和卵石出口管的热膨胀引起的相对运动由滑动接头补偿。 同时，确保必要的紧密密封。

    Pressure vessel assembly for high-temperature nuclear reactor
    4.
    发明授权
    Pressure vessel assembly for high-temperature nuclear reactor 失效
    用于高温核反应堆的压力容器组件

    公开(公告)号：US4227968A

    公开(公告)日：1980-10-14

    申请号：US1391

    申请日：1979-01-05

    申请人： Erik Bodmann

    发明人： Erik Bodmann

    IPC分类号： G21C1/12 ,  B21C23/00 ,  G21C13/00 ,  G21C13/087 ,  G21C5/00

    CPC分类号： B21C23/005 ,  G21C13/087 ,  Y02E30/40

    摘要： A nuclear-reactor assembly comprising a pressure vessel for the nuclear reactor and auxiliary vessels disposed in annularly spaced relationship around the reactor pressure vessel and communicating therewith by horizontal passages in the walls between the vessels. According to the invention, the outer surface of the reactor pressure vessel, which is otherwise generally cylindrical, is formed with vertical surfaces in the region of the passages against which complementary vertical planar surfaces of the auxiliary vessels lie. The spaces between the auxiliary vessels are filled in the plane of these passages by support blocks so that the blocks together with the auxiliary vessels form a compound disk which is prestressed inwardly by a peripheral prestressing element passing around the perimeter of the disk.

    摘要翻译： 一种核反应堆组件，其包括用于核反应堆的压力容器和在反应器压力容器周围以环形隔开的关系设置的辅助容器，并通过容器之间的壁中的水平通道与其连通。 根据本发明，反应堆压力容器的外表面通常是圆柱形的，在辅助容器的互补垂直平面所在的区域中形成垂直表面。 辅助容器之间的空间通过支撑块填充在这些通道的平面中，使得块与辅助容器一起形成复合盘，该复合盘由围绕盘的周边通过的周边预应力元件向内预应力。

    Nuclear reactor with fuel column coolant regulation
    5.
    发明授权
    Nuclear reactor with fuel column coolant regulation 失效
    具有燃料柱冷却剂调节的核反应堆

    公开(公告)号：US4121973A

    公开(公告)日：1978-10-24

    申请号：US641646

    申请日：1975-12-17

    申请人： Karol J. Mysels ,  Arkal S. Shenoy

    发明人： Karol J. Mysels ,  Arkal S. Shenoy

    IPC分类号： G21C1/12 ,  G21C5/02 ,  G21C5/06 ,  G21C15/02 ,  G21C15/08

    CPC分类号： G21C15/02 ,  G21C5/02 ,  Y02E30/40

    摘要： A nuclear reactor is described in which a core having a plurality of columnar fuel regions with coolant passages therein and valve means for each fuel region regulating, separately, the flow of coolant therethrough, is provided with collecting means at the downstream ends of the passages. The collecting means define a plurality of discharge orifices and a plurality of intake means, one for each of the discharge orifices. Each of the intake means commingles a portion of the coolant from each of a plurality of adjacent fuel regions in a respective one of the discharge orifices.

    摘要翻译： 描述了一种核反应器，其中具有多个具有冷却剂通道的柱状燃料区域的芯体以及用于各个燃料区域的阀装置单独地调节冷却剂流动的阀装置在通道的下游端设置有收集装置。 收集装置限定多个排放孔和多个进气装置，每个排出孔一个。 每个进气装置将一部分冷却剂从相应的一个排放孔中的多个相邻燃料区域中的每一个排出。

    Nuclear powerplant with closed gas-cooling circuit for production of process heat
    7.
    发明授权
    Nuclear powerplant with closed gas-cooling circuit for production of process heat 失效
    核动力装置用封闭气体冷却回路生产工艺热量

    公开(公告)号：US4022659A

    公开(公告)日：1977-05-10

    申请号：US556425

    申请日：1975-03-07

    申请人： Heinrich Baumgaertner

    发明人： Heinrich Baumgaertner

    IPC分类号： G21C1/12 ,  G21C1/00 ,  G21C1/32 ,  G21D1/04 ,  G21D5/08 ,  G21C3/56

    CPC分类号： G21C1/326 ,  Y02E30/40

    摘要： A power plant having a closed gas-cooling circuit for the production of process heat to be transferred to a secondary circuit, comprising: (a) a vessel comprising a generally solid block of material; (b) a high-temperature reactor positioned within the vessel; (c) a plurality of heat exchanger units positioned about said reactor in the reactor in the vessel, the heat exchanger units comprising each a high temperature heat exchanger and a low temperature heat exchanger coupled serially therewith, each of the heat exchanger units being removably mounted in a vertically oriented shaft in the material; (d) first means for conducting a portion of a hot gas stream leaving the reactor to each of the high temperature heat exchangers where the hot gas is partially cooled by indirect contact with a working fluid in the secondary circuit; (e) second means for conducting said cooled gas from each of the high temperature heat exchangers to said low temperature heat exchangers coupled therewith where the gas is further cooled by indirect contact with the secondary circuit fluid; and means for returning said further cooled gas to the reactor from each of the low temperature heat exchangers by circulating the gas around the periphery of each respective heat exchanger unit.

    摘要翻译： 一种具有封闭的气体冷却回路的发电厂，用于生产工艺热量以传递到次级回路，包括：（a）容器，其包括一般固体的材料块; （b）位于容器内的高温反应器; （c）多个热交换器单元，其位于容器内的反应器中的所述反应器周围，热交换器单元包括高温热交换器和与其串联连接的低温热交换器，每个热交换器单元可移除地安装 在材料中垂直取向的轴; （d）第一装置，用于将离开反应器的一部分热气流引导到每个高温热交换器，其中热气体通过与次级回路中的工作流体的间接接触部分地冷却; （e）第二装置，用于将来自每个高温热交换器的所述冷却气体导引到与其连接的所述低温热交换器，其中气体通过与次级回路流体的间接接触进一步冷却; 以及用于使每个各个热交换器单元的周边周围的气体循环，使来自每个低温热交换器的所述另外冷却的气体返回到反应器的装置。

    Steam cooled nuclear reactor
    8.
    发明授权
    Steam cooled nuclear reactor 失效
    蒸汽冷却核反应堆

    公开(公告)号：US3660231A

    公开(公告)日：1972-05-02

    申请号：US3660231D

    申请日：1968-11-26

    申请人： GEN ELECTRIC

    发明人： FOX JACK N ,  HANSEN NED P ,  OLICH EUGENE E ,  GUENTHER RALPH W ,  RUBINSTEIN HERBERT J

    IPC分类号： G21C1/12 ,  G21C3/14 ,  G21C3/32 ,  G21C7/10 ,  G21C7/103 ,  G21C11/06 ,  G21C15/00 ,  G21D5/06

    CPC分类号： G21C1/12 ,  G21C3/14 ,  G21C3/32 ,  G21C7/10 ,  G21C7/103 ,  G21C11/06 ,  G21C15/00 ,  G21D5/06 ,  G21Y2002/201 ,  G21Y2002/402 ,  G21Y2004/30 ,  G21Y2004/302 ,  Y02E30/33 ,  Y02E30/39

    摘要： A nuclear reactor pressure vessel internals arrangement including a core assembly, control means and steam flow directing means is disclosed. The reactor utilizes a two-pass steam flow scheme in which steam flows downwardly through non-fueled core components and then flows upwardly through the fuel assemblies. The reactor internals are located within a shroud which forms a second pressure-tight vessel. Water located in an annular space between the internal shroud and the main pressure vessel provides additional shielding and is readily available for core flooding. The arrangement provides improved safety, simplicity and reliability in steam cooled reactor operation.

    摘要翻译： 公开了包括芯组件，控制装置和蒸汽流引导装置的核反应堆压力容器内部装置。 反应器采用两通蒸汽流动方案，其中蒸汽向下流过非燃料核心部件，然后向上流过燃料组件。 反应器内部件位于形成第二压力容器的护罩内。 位于内部护罩和主压力容器之间的环形空间中的水提供额外的屏蔽，并且容易用于芯浸。 该装置提高了蒸汽冷却反应堆运行中的安全性，简便性和可靠性。