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    Nuclear reactor core and fuel element therefor
    1.
    发明授权
    Nuclear reactor core and fuel element therefor 失效
    核反应堆核心和燃料元件

    公开(公告)号：US4569820A

    公开(公告)日：1986-02-11

    申请号：US263300

    申请日：1981-05-13

    Applicant: Peter Fortescue

    Inventor： Peter Fortescue

    IPC: G21C3/00 ,  G21C15/08

    CPC classification number: G21C3/00 ,  G21C15/08 ,  Y02E30/40

    Abstract: The present invention relates to a nuclear reactor core and fuel elements therefore. Stackable fuel elements, having the usual coolant holes machined therethrough, are formed with grooves along their vertical extent for alignment with similar grooves on adjacent fuel elements to define additional coolant passageways. These grooves provide coolant passageways between adjacent fuel elements enhancing the mechanical stability of the core. Furthermore, these additional coolant passageways allow a more efficient utilization of reactor core space and permit coolant escaping into the interstices between adjacent ends of blocks to be collected at these additional coolant passageways. Stability may be enhanced further by means of complementary elevations and depressions formed on end faces of the fuel blocks.

    Abstract translation: 本发明涉及核反应堆核心和燃料元件。 具有通过其加工的通常的冷却剂孔的可堆叠燃料元件沿其垂直方向形成有凹槽，用于与相邻燃料元件上的相似凹槽对准以限定额外的冷却剂通道。 这些凹槽在相邻的燃料元件之间提供冷却剂通道，增强了芯的机械稳定性。 此外，这些额外的冷却剂通道允许更有效地利用反应堆堆芯空间并允许冷却剂逸出到在这些另外的冷却剂通道处被收集的块的相邻端之间的间隙中。 通过在燃料块的端面上形成的互补的高度和凹陷可以进一步增强稳定性。

    Boron thermal regeneration system
    2.
    发明授权
    Boron thermal regeneration system 失效
    硼热再生系统

    公开(公告)号：US4017358A

    公开(公告)日：1977-04-12

    申请号：US591781

    申请日：1975-06-26

    Applicant: Martinus R. Van der Schoot

    Inventor： Martinus R. Van der Schoot

    IPC: G21C7/22 ,  G21C15/00 ,  G21C15/08

    CPC classification number: G21C7/22 ,  G21C15/00 ,  Y02E30/39

    Abstract: An ion exchanger which allows flow in both directions along a selected flow-path. A separator plate divides the exchanger tank into two chambers each of which has a flow-conduit so that flow may enter or leave from either chamber while prohibiting the resin particles from migrating from one side of the tank to the other. This ion exchanger permits a dual-directional flow-process to be practiced which results in immediate changes in the boron concentration within a nuclear reactor coolant system even if the ion-exchanger resins have not been completely equilibrated during a previous operation.

    Abstract translation: 允许沿着选定的流动路径沿两个方向流动的离子交换器。 分隔板将交换器槽分成两个室，每个室具有流动导管，使得流动可以从任一室进入或离开，同时禁止树脂颗粒从罐的一侧迁移到另一个室。 该离子交换器允许实施双向流动过程，这导致核反应堆冷却剂系统内的硼浓度的立即变化，即使离子交换树脂在先前操作期间尚未完全平衡。

    Variable propellant density for passive reactivity control of nuclear thermal propulsion reactors
    4.
    发明授权
    Variable propellant density for passive reactivity control of nuclear thermal propulsion reactors 有权

    公开(公告)号：US11417437B2

    公开(公告)日：2022-08-16

    申请号：US16818320

    申请日：2020-03-13

    Applicant: ULTRA SAFE NUCLEAR CORPORATION

    Inventor： Paolo Francesco Venneri ,  Michael John Eades

    IPC: G21D5/02 ,  B64G1/40 ,  G21C5/02 ,  G21C15/08 ,  G21C3/62 ,  G21C3/38 ,  G21C15/06 ,  G21C3/64 ,  G21C7/04

    Abstract: Passive reactivity control technologies that enable reactivity control of a nuclear thermal propulsion (NTP) system with little to no active mechanical movement of circumferential control drums. By minimizing or eliminating the need for mechanical movement of the circumferential control drums during an NTP burn, the reactivity control technologies simplify controlling an NTP reactor and increase the overall performance of the NTP system. The reactivity control technologies mitigate and counteract the effects of xenon, the dominant fission product contributing to reactivity transients. Examples of reactivity control technologies include, employing burnable neutron poisons, tuning hydrogen pressure, adjusting wait time between burn cycles or merging burn cycles, and enhancement of temperature feedback mechanisms. The reactivity control technologies are applicable to low-enriched uranium NTP systems, including graphite composite fueled and tungsten ceramic and metal matrix (CERMET), or any moderated NTP system, such as highly-enriched uranium graphite composite NTP systems.

    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

    Applicant: Karol J. Mysels ,  Arkal S. Shenoy

    Inventor： Karol J. Mysels ,  Arkal S. Shenoy

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

    CPC classification number: G21C15/02 ,  G21C5/02 ,  Y02E30/40

    Abstract: 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.

    Abstract translation: 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。

    DEVICES, SYSTEMS, AND METHODS FOR COOLING A NUCLEAR REACTOR WITH HYDRIDE MODERATORS
    10.
    发明公开
    DEVICES, SYSTEMS, AND METHODS FOR COOLING A NUCLEAR REACTOR WITH HYDRIDE MODERATORS 审中-公开

    公开(公告)号：US20240233966A1

    公开(公告)日：2024-07-11

    申请号：US18153247

    申请日：2023-01-11

    Applicant: Westinghouse Electric Company LLC

    Inventor： Alexander Whitecross HARKNESS

    IPC: G21C5/12 ,  G21C15/08 ,  G21C15/257

    CPC classification number: G21C5/12 ,  G21C15/08 ,  G21C15/257

    Abstract: A heat exchanger for cooling a nuclear reactor core is disclosed herein. The heat exchanger can include a first stage including an input configured to receive a working fluid from an external source into the heat exchanger, and a first plenum configured to envelope a moderator heat pipe extending from the nuclear reactor core. The heat exchanger can further include a second stage including an output configured to remove a working fluid from the heat exchanger to the external source, and a second plenum configured to envelope a power heat pipe extending from the nuclear reactor core, wherein the first plenum and the second plenum are in fluid communication and configured such that the external fluid must traverse the first plenum and over the moderator heat pipe before entering the second plenum and traversing over the power heat pipe.

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