Reactor shroud joint
    51.
    发明授权
    Reactor shroud joint 失效
    反应器护罩接头

    公开(公告)号:US5737378A

    公开(公告)日:1998-04-07

    申请号:US669879

    申请日:1996-06-21

    IPC分类号: G21C5/10 G21C13/02 G21C13/00

    摘要: A shroud for a nuclear reactor is described. In one embodiment, the shroud includes first and second shroud sections, and each shroud section includes a substantially cylindrical main body having a first end and a second end. With respect to each shroud section, a flange is located at the main body first end, and the flange has a plurality of bolt openings therein and a plurality of scalloped regions. The first shroud section is welded to the second shroud section, and at least some of the bolt openings in the first shroud section flange align with respective bolt openings in the second shroud section flange. In the event that the onset of inter-granular stress corrosion cracking is ever detected in the weld between the shroud section, bolts are inserted through bolt openings in the first shroud section flange and through aligned bolt openings the second shroud section flange. Each bolt, in one embodiment, has a shank section and first and second threaded end sections. Nuts are threadedly engaged to the threaded end sections and tightened against the respective flanges.

    摘要翻译: 描述了用于核反应堆的护罩。 在一个实施例中,护罩包括第一和第二护罩部分,并且每个护罩部分包括具有第一端和第二端的基本上圆柱形的主体。 对于每个护罩部分,凸缘位于主体第一端,并且凸缘在其中具有多个螺栓开口和多个扇形区域。 第一护罩部分焊接到第二护罩部分,并且第一护罩部分凸缘中的至少一些螺栓开口与第二护罩部分凸缘中的相应的螺栓孔对准。 如果在护罩部分之间的焊缝中检测到颗粒间应力腐蚀开裂,则螺栓通过第一护罩部分凸缘中的螺栓孔插入并通过对准的螺栓孔插入第二护罩部分凸缘。 在一个实施例中,每个螺栓具有柄部分和第一和第二螺纹端部部分。 螺母螺纹接合到螺纹端部并且紧固在相应的凸缘上。

    Tool for remotely installing and torquing tie rod nut with limited
vertical access
    52.
    发明授权
    Tool for remotely installing and torquing tie rod nut with limited vertical access 失效
    用于远程安装和扭矩拉杆螺母的工具,具有有限的垂直通道

    公开(公告)号:US5690005A

    公开(公告)日:1997-11-25

    申请号:US532201

    申请日:1995-09-22

    摘要: A tool for installing and torquing a tensioning nut onto a tie rod of a shroud repair apparatus. The nut torquing tool has a socket for coupling with the tensioning nut and an adaptor for coupling with a manually operated handling pole, wherein the axis of rotation of the socket is radially displaced relative to the axis of rotation of the adaptor. The respective shafts connected to the socket and adaptor are coupled by means of a pair of sprockets and a chain which convert rotation of the adaptor into rotation of the socket. The distance between the sprockets can be adjusted to tension the chain. The handling pole adaptor is connected to a drive shaft by way of a universal joint, a torque limiter and a torque multiplier. Incorporation of a torque multiplier facilitates installation and torquing of the tensioning nut in a single operation using a lightweight handling pole.

    摘要翻译: 用于将张紧螺母安装和扭转到护罩修理装置的拉杆上的工具。 螺母扭力工具具有用于与张紧螺母联接的插座和用于与手动操作的操纵杆联接的适配器,其中插座的旋转轴线相对于适配器的旋转轴线径向移位。 连接到插座和适配器的各个轴通过一对链轮和链条联接,该链条将适配器的旋转转换成插座的旋转。 可以调节链轮之间的距离,以拉紧链条。 操纵杆适配器通过万向节,扭矩限制器和扭矩倍增器连接到驱动轴。 扭矩乘法器的结合有助于在单个操作中使用轻便的操纵杆来安装和扭转张紧螺母。

    Underwater remote drilling tool and methods
    53.
    发明授权
    Underwater remote drilling tool and methods 失效
    水下远程钻探工具及方法

    公开(公告)号:US5687205A

    公开(公告)日:1997-11-11

    申请号:US529229

    申请日:1995-09-15

    IPC分类号: G21C5/10 G21C19/00

    摘要: A remotely operated drilling tool is configured to produce holes in a core shroud support plate inside of a nuclear reactor vessel. The tool includes a support base that is securely mounted directly above the location where the hole will be formed. In a first operation, a drilling tool is secured to the support base and drills a hole through about 90% of the shroud support plate. The drilling tool includes chip capturing structure to prevent chip created by the machining process from contaminating the water in the reactor vessel. After about 90% of the hole is drilled with the drilling tool, an EDM tool is secured to the support base to machine the remainder of the hole using an EDM process. The EDM tool includes structure for machining the remainder of the hole, removing the slug from the hole, and performing a spotface on the underside of the shroud support plate. The underwater drilling tool is capable of producing high quality holes faster and more efficiently than the current EDM process, while maintaining control of all foreign material, minimizing the deleterious effects on the material being drilled, and reducing the risk associated with poor tool reliability and breakage.

    摘要翻译: 远程操作的钻具被配置为在核反应堆容器内的核心护罩支撑板上产生孔。 该工具包括一个可靠地安装在孔形成位置正上方的支撑底座。 在第一操作中,钻具被固定到支撑基座上并钻孔穿过护罩支撑板的大约90%。 钻孔工具包括芯片捕获结构,以防止由加工过程产生的芯片污染反应堆容器中的水。 在使用钻孔工具钻孔的大约90%之后,EDM工具被固定到支撑基座上,以使用EDM工艺加工其余的孔。 EDM工具包括用于加工孔的其余部分的结构,从孔中除去芯块,以及在护罩支撑板的下侧上执行点表面。 水下钻具能够比当前的EDM工艺更快,更有效地生产高质量的孔,同时保持对所有异物的控制,最大限度地减少对被钻探材料的有害影响,并减少与不良工具可靠性和破损相关的风险 。

    Tool for installing hardware for radially supporting vertical restraint
tie rod
    54.
    发明授权
    Tool for installing hardware for radially supporting vertical restraint tie rod 失效
    用于安装用于径向支撑垂直约束拉杆的硬件的工具

    公开(公告)号:US5600688A

    公开(公告)日:1997-02-04

    申请号:US532910

    申请日:1995-09-22

    申请人: Wing G. Jung

    发明人: Wing G. Jung

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

    摘要: A tool for installing a support member which must be rotated into a horizontal position in the downcomer annulus of a boiling water reactor by remote manipulation. The support member may, for example, be a midsupport for damping flow-induced vibrations in a vertical restraint tie rod. The tool includes a rigid holder for holding the support member and a threaded pivot for coupling with the threaded end of a cable. The pivot can swing relative to the holder between first and second angular positions separated by 90.degree.. The support member is held in the holder by a pair of channels formed on the holder and a set screw which threads in the holder and enters a bore formed in the support member. After the support member has been secured to the holder, the holder is coupled to the end of the cable via the pivot. The support member is lowered in the downcomer annulus in a vertical position. When the support member reaches the installation elevation, the support member is pivoted into a horizontal position for engagement with the tie rod. The tool is disengaged from the installed support member by remote manipulation of the set screw.

    摘要翻译: 用于安装支撑构件的工具,该支撑构件必须通过远程操纵旋转到沸水反应堆的降液管环中的水平位置。 支撑构件可以例如是用于阻止垂直约束拉杆中的流动振动的中间支撑。 该工具包括用于保持支撑构件的刚性保持器和用于与电缆的螺纹端连接的螺纹枢轴。 枢轴在相隔90°的第一和第二角度位置之间相对于支架摆动。 支撑构件通过形成在保持器上的一对通道和固定螺钉保持在保持器中,该螺钉在保持器中螺纹并进入形成在支撑构件中的孔中。 在支撑构件已经固定到保持器之后,保持器经由枢轴联接到电缆的端部。 支撑构件在垂直位置下降到降液管环中。 当支撑构件到达安装高度时,支撑构件枢转到水平位置以与拉杆接合。 通过远程操作固定螺丝,该工具与安装的支撑构件脱离接合。

    Method for detecting changes in preload on a tie rod installed as part
of a core shroud repair in a boiling water reactor
    55.
    发明授权
    Method for detecting changes in preload on a tie rod installed as part of a core shroud repair in a boiling water reactor 失效
    用于检测在沸水反应器中安装作为核心护罩修复的一部分的拉杆上的预载荷变化的方法

    公开(公告)号:US5589640A

    公开(公告)日:1996-12-31

    申请号:US627154

    申请日:1996-04-03

    申请人: Patrick J. Butler

    发明人: Patrick J. Butler

    摘要: In a boiling water reactor having a core shroud disposed within a reactor vessel and a plurality of tie rods installed between vertically spaced sites on the core shroud as part of a core shroud repair, a method of measuring tie rod preload after installation includes the steps of lowering a tool into the reactor vessel from a remote location positioned externally of the reactor vessel, attaching the tool to an upper portion of a tie rod, using the tool to apply a tensile load along a longitudinal axis of the tie rod, measuring the tensile load applied to the tie rod, measuring axial displacement of the tie rod in response to the applied tensile load, plotting the applied load versus the axial displacement measured, and identifying a change in slope on the load-displacement plot occurring at a load corresponding to the tie rod preload.

    摘要翻译: 在具有设置在反应器容器内的芯护罩的沸水反应器中,以及安装在芯护罩上的垂直间隔位置之间的多个拉杆作为芯护罩修复的一部分,在安装后测量拉杆预载荷的方法包括以下步骤: 将工具从位于反应堆外部的远程位置降低到反应堆容器中,使用该工具将工具连接到拉杆的上部,以沿着拉杆的纵向轴线施加拉伸载荷,测量拉伸强度 施加到拉杆上的载荷,测量拉杆响应于所施加的拉伸载荷的轴向位移,绘制所施加的载荷相对于所测量的轴向位移,并且识别在相应于该载荷的载荷下发生的载荷 - 位移图上的斜率变化 拉杆预紧。

    Removable shroud and pump deck for a boiling water nuclear reactor
    56.
    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:US5519744A

    公开(公告)日:1996-05-21

    申请号:US354736

    申请日:1994-12-06

    申请人: Charles W. Relf

    发明人: Charles W. Relf

    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,其中护罩可移除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。

    Process and device for limiting the intensity of parasitic jets of
cooling water in a pressurized-water nuclear reactor
    57.
    发明授权
    Process and device for limiting the intensity of parasitic jets of cooling water in a pressurized-water nuclear reactor 失效
    用于限制加压水核反应堆中冷却水的寄生射流强度的方法和装置

    公开(公告)号:US4997620A

    公开(公告)日:1991-03-05

    申请号:US318879

    申请日:1989-03-06

    IPC分类号: G21C15/02 G21C5/10 G21C15/10

    CPC分类号: G21C15/10 G21C5/10 Y02E30/40

    摘要: During a shutdown of the reactor, a device for partially closing off (27) the openings (26) of the reinforcements (6) located below the upper reinforcement (6a) is introduced through the opening (25) of the upper reinforcement (6a) of the partitioning of the core of the reactor. The closing off devices (27) remaining in position in the partitioning of the reactor after restarting thereof permit the increase and regulation of the head loss of the cooling water circulating in the annular space (7) around the partitioning (5) of the core. The closing-off device may consist of a rod (27) engaged in a set of openings (26) of the reinforcements (6) aligned along a vertical direction.

    摘要翻译: 在反应堆关闭期间,用于部分闭合(27)位于上部加强件(6a)下方的加强件(6)的开口(26)的装置通过上部加强件(6a)的开口(25)引入, 的反应堆核心的分配。 在重新启动之后在反应器分隔中保持就位的关闭装置(27)允许增加和调节围绕芯的分隔(5)的环形空间(7)中循环的冷却水的头部损失。 关闭装置可以由接合在沿着垂直方向对准的增强件(6)的一组开口(26)中的杆(27)组成。

    Modular lining for adapting the containment to the core of a pressurized
water nuclear reactor
    58.
    发明授权
    Modular lining for adapting the containment to the core of a pressurized water nuclear reactor 失效
    用于使密封件适应于加压水核反应堆核心的模块衬里

    公开(公告)号:US4701299A

    公开(公告)日:1987-10-20

    申请号:US568465

    申请日:1984-01-05

    IPC分类号: G21C5/10 G21C5/08 G21C9/00

    CPC分类号: G21C5/08 Y02E30/40

    摘要: A modular lining for adapting the containment to the core of a pressurized water nuclear reactor, consisting of juxtaposed modular blocks (5) placed between the core containment (1) and the outer surface of the core (3). Arranged between the adjacent faces of the blocks (5), there are thin packing pieces (8) maintaining a certain gap between the undrilled solid blocks (5). The blocks (5) are fixed non-contiguously to the core containment (1) by screw devices (10) cooled by water circulation. The invention applies in particular to pressurized water nuclear reactors of improved efficiency and with a varying neutron spectrum.

    摘要翻译: 一种用于将容纳物调节到加压水核反应堆核心的模块衬里,其由放置在芯容纳体(1)和芯部(3)的外表面之间的并置的模块化块(5)组成。 在块(5)的相邻面之间布置有薄的包装片(8),在未磨碎的固体块(5)之间保持一定的间隙。 块体(5)通过水循环冷却的螺旋装置(10)与芯容纳体(1)非连续地固定。 本发明特别适用于提高效率和不同中子光谱的加压水核反应堆。

    Fast breeder reactor
    59.
    发明授权
    Fast breeder reactor 失效
    快速增殖反应堆

    公开(公告)号:US4681726A

    公开(公告)日:1987-07-21

    申请号:US663981

    申请日:1984-10-23

    摘要: A fast breeder reactor has a nuclear reactor container filled with a liquid metal, a reactor core disposed within the nuclear reactor container, and a first supporting structural member which is mounted to the nuclear reactor container such as to support the reactor core. The fast breeder reactor is provided with a cylindrical structural member which surrounds the periphery of the reactor core such as to define an annular gap between the cylindrical structural member and the reactor core for allowing the liquid metal to exist therein, the cylindrical structural member being mounted to the nuclear reactor container by means of a second supporting structural member. The inertial resisting force produced when the liquid metal existing in the annular gap will flow out from the annular gap in response to the vibration of the reactor core acts such as to suppress the vibration of the reactor core, thereby allowing an improvement in the anti-vibration properties of the fast breeder reactor.

    摘要翻译: 快速增殖反应器具有填充有液态金属的核反应堆容器,设置在核反应堆容器内的反应堆核心,以及安装在核反应堆容器上以支撑反应堆堆芯的第一支撑结构件。 快速增殖反应器设置有圆柱形结构构件,其围绕反应堆芯的周边,以便在圆柱形结构构件和反应堆芯之间限定一个环形间隙,用于允许液态金属存在于其中,圆柱形构件被安装 通过第二支撑结构构件到达核反应堆容器。 当存在于环形间隙中的液态金属响应于反应堆芯的振动而产生的惯性阻力作用为抑制反应堆堆芯的振动, 快速增殖反应堆的振动特性。