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
    6.
    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
    7.
    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。

    Core shroud, in particular for cladding a reactor core in a
boiling-water nuclear reactor and a method for repairing a core shroud
    8.
    发明授权
    Core shroud, in particular for cladding a reactor core in a boiling-water nuclear reactor and a method for repairing a core shroud 失效
    核心护罩,特别是用于在沸水核反应堆中包覆反应堆核心以及修复核心护罩的方法

    公开(公告)号:US5729581A

    公开(公告)日:1998-03-17

    申请号:US818318

    申请日:1997-03-14

    IPC分类号: G21C5/10 G21C19/02 G21C19/00

    摘要: Core shrouds are conventionally welded together from cylindrical parts and annular flanges, wherein cracks have recently occurred in the region of weld seams in reactors of the boiling-water type. A core shroud, in particular for cladding a reactor core in a boiling-water nuclear reactor and a method for repairing a core shroud, include recesses disposed transversely relative to the circumferentially extending weld seams. The recesses have a middle part which passes through a region that is thermally influenced during welding as well as transverse grooves or widenings located in front of ends of the middle part and lying outside the thermally influenced region. A clamp which is fitted into the recess is disposed approximately flush with a shroud surface and is wedged in one of the transverse grooves.

    摘要翻译: 核心护罩通常由圆柱形部件和环形凸缘焊接在一起,其中最近在沸水型反应器中的焊缝区域中出现裂纹。 特别是用于在沸水核反应堆中包覆反应堆核心的核心护罩和用于修复芯护罩的方法包括相对于周向延伸的焊缝横向设置的凹槽。 这些凹部具有穿过焊接时受热影响的区域的中间部分以及位于中间部分的前端并位于受热影响区域外部的横向槽或开口。 装配到凹部中的夹具大致与护罩表面齐平并楔入一个横向槽中。

    Removable shroud and pump deck for a boiling water nuclear reactor
    9.
    发明授权
    Removable shroud and pump deck for a boiling water nuclear reactor 失效
    用于沸水核反应堆的可拆卸护罩和泵甲板

    公开(公告)号:US5659590A

    公开(公告)日:1997-08-19

    申请号:US635555

    申请日:1996-04-22

    摘要: In a pressure vessel of a nuclear reactor containing a core assembly enclosed within a core shroud, the core shroud spaced radially inwardly of a side wall of the pressure vessel with an annular pump deck located in an annular radial space between the core shroud and the side wall of the pressure vessel, the improvement wherein the shroud is removably secured to an annular support leg extending upwardly from the bottom of the pressure vessel; and further wherein the annular pump deck is provided in the form of a plurality of removable segments.

    摘要翻译: 在核反应堆的压力容器中,该核反应堆包含封闭在核心护罩内的芯组件,所述芯护罩与压力容器的侧壁径向向内隔开,环形泵板位于芯护罩和侧面之间的环形径向空间中 压力容器的壁,其中护罩可拆卸地固定到从压力容器的底部向上延伸的环形支撑腿的改进; 并且进一步地,其中所述环形泵板以多个可移除段的形式提供。

    Lateral restraint for core plate of boiling water reactor
    10.
    发明授权
    Lateral restraint for core plate of boiling water reactor 失效
    开水反应堆核心板的侧向约束

    公开(公告)号:US5502754A

    公开(公告)日:1996-03-26

    申请号:US382748

    申请日:1995-02-02

    申请人: John G. Erbes

    发明人: John G. Erbes

    摘要: An apparatus for stabilizing a core plate against lateral deflection. A plurality of core plate wedge assemblies (e.g., four) are installed in the circumferential gap between the circular outer peripheral edge of the core plate and the circular cylindrical wall of the middle shell of the shroud at respective azimuthal positions. These core plate wedge assemblies are wedged into place with preload to maintain the spacing between the core plate and the shroud, thereby maintaining the alignment of the fuel assemblies. The core plate wedge assemblies further serve to transmit loads from the nuclear fuel core to the core shroud at azimuthal locations where lateral shroud restraints outside the shroud contact the reactor pressure vessel.

    摘要翻译: 一种用于使芯板稳定抵抗横向偏转的装置。 多个芯板楔形组件(例如,四个)安装在芯板的圆形外周边缘与护罩的中间壳体的圆柱形壁之间的圆周间隙中,在相应的方位角位置。 这些芯板楔组件被楔入到预定的位置以保持芯板和护罩之间的间隔,从而保持燃料组件的对准。 芯板楔组件还用于将负载从核燃料芯传递到芯护罩,方位角位置处的护罩外的侧护罩限制器接触反应堆压力容器。