Micro-reactor core mechanical support

    公开(公告)号:US11810681B2

    公开(公告)日:2023-11-07

    申请号:US18155193

    申请日:2023-01-17

    摘要: A nuclear reactor core mechanical support bracket is disclosed. The support bracket includes a housing, a spring disposed internally within the housing, a shaft slidingly disposed within the housing, a shaft travel pin, and a flange. The shaft is configured to engage the spring to compress and decompress the spring as the shaft travels in and out of the housing. The shaft travel pin controls the travel of the shaft. The flange is configured to mount the nuclear reactor core mechanical support bracket to a canister of a nuclear reactor. The shaft includes an inset configured to interface with a nuclear reactor core component.

    NUCLEAR REACTOR SYSTEM WITH LIFT-OUT CORE ASSEMBLY

    公开(公告)号:US20230268091A1

    公开(公告)日:2023-08-24

    申请号:US18123949

    申请日:2023-03-20

    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.

    Nuclear reactor assembly having a reversible weldless connection between a casing and an element inserted therein

    公开(公告)号:US10902957B2

    公开(公告)日:2021-01-26

    申请号:US16029107

    申请日:2018-07-06

    摘要: An assembly to be inserted into a nuclear reactor, such as a liquid sodium-cooled fast neutron reactor, includes an assembly hollow body of elongate shape along a longitudinal axis X. The wall of the hollow body includes at least one through-opening. The assembly also includes an assembly element inserted into the hollow body. The assembly element includes at least one flexible blade of which the free end is shaped into a clip-fastening hook collaborating in clip-fastening fashion with the through-opening from inside the hollow body, so as to connect the assembly element to the hollow body. The assembly also includes at least one removable structure for locking the flexible blade clip-fastened into the through-opening. The removable locking structure makes it possible to prevent the flexible blade from flexing and thus the removable locking structure makes it possible to lock a connection between the assembly element and the hollow body.

    Nuclear Reactor Support And Seismic Restraint With In-Vessel Core Retention Cooling Features

    公开(公告)号:US20180082759A1

    公开(公告)日:2018-03-22

    申请号:US15675850

    申请日:2017-08-14

    申请人: BWXT mPower, Inc.

    摘要: A nuclear island includes a nuclear reactor, a lateral seismic restraint, and an in-vessel reactor core retention cooling system. The lateral seismic restraint includes a vertically oriented pin attached to one of the bottom of the lower vessel head and the floor underneath the nuclear reactor, and a mating pin socket is attached to the other of the bottom of the lower vessel head and the floor. The in-vessel reactor core retention cooling system includes one or more baffles, optionally thermally insulating material, disposed alongside the exterior surface of a lower portion of the reactor pressure vessel including at least the lower vessel head. A plenum is defined between the one or more baffles and the exterior surface of a lower portion of the reactor pressure vessel. The one or more baffles may define a lower plenum inlet surrounding the lateral seismic restraint.

    Method and apparatus for refueling a nuclear reactor having an instrumentation penetration flange
    9.
    发明授权
    Method and apparatus for refueling a nuclear reactor having an instrumentation penetration flange 有权
    用于对具有仪器穿透法兰的核反应堆进行加油的方法和装置

    公开(公告)号:US09064607B2

    公开(公告)日:2015-06-23

    申请号:US13742392

    申请日:2013-01-16

    IPC分类号: G21C19/10 G21C5/10 G21C1/32

    摘要: Apparatus and a method for retracting in-core instrument thimble tubes from the reactor core prior to refueling a nuclear reactor with top mounted instrumentation. The apparatus includes a penetration flange interposed between the head flange and the reactor vessel flange through which the instrumentation cabling passes. The penetration flange is connected to the upper internals and can be raised relative thereto to retract instrumentation thimbles from the core prior to removal of the upper internals from the reactor vessel for refueling. The penetration flange is removed from the vessel with the upper internals.

    摘要翻译: 在使用顶部安装的仪器加油核反应堆之前,从反应堆堆芯回收核心内仪器套管的装置和方法。 该装置包括插入在头部凸缘和仪器电缆穿过的反应堆容器凸缘之间的穿透凸缘。 穿透法兰连接到上内部并且可以相对于其上升高,以在从反应堆容器移除上部内部件之前从芯部缩回装置套管,用于加油。 穿透法兰从上部内部从容器中取出。

    Reactor core shroud repair using thermally tensioned links to apply
compression across shroud vertical seam weld
    10.
    发明授权
    Reactor core shroud repair using thermally tensioned links to apply compression across shroud vertical seam weld 失效
    使用热张力链接的反应堆芯护罩修复在横向纵向缝焊上施加压力

    公开(公告)号:US6067338A

    公开(公告)日:2000-05-23

    申请号:US804722

    申请日:1997-02-21

    申请人: John Geddes Erbes

    发明人: John Geddes Erbes

    IPC分类号: G21C5/10 G21C19/00

    摘要: An apparatus for repairing the core shroud of a nuclear reactor having one or more cracked vertical seam welds. The repair involves machining two holes in the shroud on opposing sides of the cracked vertical seam weld and then attaching two flexible links on the inside and outside of the shroud wall by means of two shear bolts inserted in the machined holes. The flexible links bridge the cracked vertical weld seam. Multiple link assemblies can be placed along the length of a crack. The links are made of an alloy having a coefficient of thermal expansion less than the coefficient of thermal expansion of the shroud material. The links are installed while the reactor is shutdown. When the reactor returns to operation, the consequent temperature rise causes the shroud section being bridged by the links to expand more than the links expand. As a result the links exert a circumferential compressive load across the crack in the vertical seam weld.

    摘要翻译: 一种用于修复具有一个或多个裂纹垂直焊缝的核反应堆的核心护罩的装置。 修理包括在裂缝垂直缝焊缝的相对侧上的护罩中加工两个孔,然后通过插入加工孔中的两个剪切螺栓在护罩壁的内部和外部附接两个柔性连接。 柔性连接桥接裂缝垂直焊缝。 多个连杆组件可以沿着裂缝的长度放置。 连接件由热膨胀系数小于护罩材料的热膨胀系数的合金制成。 在反应堆关闭时安装链接。 当反应堆返回操作时,随之而来的温度升高导致通过连接件桥接的护罩部分比连杆膨胀更多。 因此,连接件在垂直焊缝中穿过裂缝施加圆周压缩载荷。