Apparatus for assembling nuclear fuel assembly
    1.
    发明授权
    Apparatus for assembling nuclear fuel assembly 失效
    装配核燃料组件的装置

    公开(公告)号:US5303273A

    公开(公告)日:1994-04-12

    申请号:US996065

    申请日:1992-12-23

    CPC classification number: G21C3/334 Y02E30/40

    Abstract: An apparatus for assembling a nuclear fuel assembly is disclosed. The apparatus includes a deflecting device which is disposed adjacent to the grid and deflects grid springs away from dimples opposing thereto. The deflecting device includes a tubular member, a rod member and a drive mechanism. The tubular member has a plurality of circumferentially divided sleeve pieces. The rod member is releasably inserted in the tubular member for sliding movement therealong. The drive mechanism is drivingly connected to the rod member and moves the rod member in the tubular member in a longitudinal direction thereof to bring the rod member into urging engagement with the sleeve pieces of the tubular member, whereby the sleeve pieces are deflected to be urged against the spring to deflect the same.

    Abstract translation: 公开了一种组装核燃料组件的装置。 该装置包括偏转装置,该偏转装置邻近格栅设置并使网格弹簧远离与其相对的凹坑。 偏转装置包括管状构件,杆构件和驱动机构。 管状构件具有多个周向分开的套筒件。 杆构件可释放地插入管状构件中,用于沿着其滑动运动。 驱动机构驱动地连接到杆构件,并且使杆构件在管状构件的纵向方向上移动,以使杆构件与管状构件的套筒件压力接合,由此套筒件被偏转以被推动 反对弹簧偏转相同。

    Apparatus for operating the grid springs of nuclear fuel assembly
    2.
    发明授权
    Apparatus for operating the grid springs of nuclear fuel assembly 失效
    用于操作核燃料组件的电网弹簧的装置

    公开(公告)号:US5303272A

    公开(公告)日:1994-04-12

    申请号:US964073

    申请日:1992-10-21

    CPC classification number: G21C3/334 Y02E30/40

    Abstract: The present invention relates to an apparatus for manipulating the springs which hold the fuel rods firmly inside the grid cells of the grids in a nuclear fuel assembly. Conventionally fuel rods are inserted into the grids while the grid springs are in the active position, thus exposing the rods to possibilities of surface scratches and potential problems. The invented automatic apparatus avoids the formation of such surface damage on the fuel rods, by inserting the keys to inactivate the grid springs before inserting the fuel rods into the grids and removing the keys after all the rods are in place. The apparatus thus contributes to efficient manufacturing of the fuel assembly by simplifying the key quantity management operations and other tasks associated with the assembling operations.

    Abstract translation: 本发明涉及一种用于操纵弹簧的装置,其将燃料棒牢固地保持在核燃料组件中格栅的格栅内。 通常,将燃料棒插入网格中,同时格栅弹簧处于活动位置,从而使杆暴露于表面划痕和潜在问题的可能性。 本发明的自动装置通过在将燃料棒插入网格之前插入钥匙来灭活栅格弹簧并且在所有杆都到位之后去除钥匙,从而避免在燃料棒上形成这种表面损伤。 因此,该装置有助于通过简化关键数量管理操作和与组装操作相关联的其他任务来有效地制造燃料组件。

    Welding apparatus for fuel rod end plugs
    4.
    发明授权
    Welding apparatus for fuel rod end plugs 失效
    燃料棒端塞焊接装置

    公开(公告)号:US5319178A

    公开(公告)日:1994-06-07

    申请号:US976338

    申请日:1992-11-13

    CPC classification number: G21C3/10 Y02E30/40

    Abstract: A welding apparatus for welding an end plug on the end of a pellet filled nuclear fuel rod includes a holding mechanism, an abutting member, a torch and a pressing mechanism. The holding mechanism is for holding the external periphery of the fuel rod with the end plug attached thereto. The abutting member is disposed opposite to the holding mechanism, and the end plug of the fuel rod butts up against the abutting member. The torch is disposed between the holding mechanism and the abutting member, and is placed diametrically opposite to the external surface of the fuel rod. The holding mechanism and the abutting member are made so that the distance therebetween can be adjusted, and the pressing mechanism is provided on one of the holding mechanism or the abutting member, and operates to move the holding mechanism and the abutting member to approach each other. In a welding apparatus of such a design, the fuel rod is held by the holding mechanism, and the pressing mechanism pushes the holding mechanism toward the abutting member, and while retaining such a position at a constant compressive force, welding of the end plug is performed. Therefore, the welding is performed without being affected by the variations in the compressive force caused by welding heat distortions, thereby providing a weld of high integrity and quality.

    Abstract translation: 用于焊接填充颗粒填充的核燃料棒的端部上的端塞的焊接装置包括保持机构,抵接构件,手电筒和按压机构。 保持机构用于保持安装有端塞的燃料棒的外周。 抵接构件与保持机构相对设置,并且燃料棒的端塞抵靠抵靠构件。 手柄设置在保持机构和抵接构件之间,并且与燃料棒的外表面径向相对设置。 保持机构和抵接构件被制成使得可以调节它们之间的距离,并且按压机构设置在保持机构或抵接构件中的一个上,并且操作以使保持机构和抵接构件相互靠近 。 在这种设计的焊接装置中,燃料棒由保持机构保持,并且按压机构将保持机构推向抵接部件,并且在以一定的压缩力保持这样的位置的同时,端塞的焊接 执行。 因此,焊接不受焊接热变形引起的压缩力的变化的影响,从而提供高完整性和高质量的焊接。

    Apparatus for assembling a nuclear fuel assembly
    5.
    发明授权
    Apparatus for assembling a nuclear fuel assembly 失效
    用于组装核燃料组件的装置

    公开(公告)号:US5274684A

    公开(公告)日:1993-12-28

    申请号:US966008

    申请日:1992-10-23

    CPC classification number: G21C3/334 Y02E30/40

    Abstract: The present invention presents a method and an apparatus for assembling a fuel assembly which is free of surface damage on the fuel rod surfaces, and of distortions caused by residual stresses. Such problems are introduced by the method of inserting the fuel rods into the grids, and the sequence of attaching the control rod guiding pipes. In the conventional method, the guiding pipes are attached to the respective grids first and the fuel rods are inserted in the grids while the holding mechanisms (such as spring force against a dimple formed on the grid wall) are active. In the invented assembling method, the sprigs are deactivated first and then the fuel rods are inserted into the grids. Once the assembly is made firm with all the fuel rods in place and fixed firmly to the grids, the control rod guiding pipes are inserted into the grids and the pipes are fixed rigidly to the respective grids. By performing the assembling operation in the above sequence, slight shifting of the grids which occurs on fixing the pipes to the grids, during the conventional method, is prevented. The final assembly produced according to the invented method is free of surface damage and the overall quality of alignment of the assembly is excellent.

    Abstract translation: 本发明提出了一种用于组装燃料组件的方法和装置,其在燃料棒表面上没有表面损伤以及由残余应力引起的变形。 这些问题是通过将燃料棒插入网格的方法和连接控制杆引导管的顺序引入的。 在常规方法中,引导管首先附接到各个格栅,并且燃料棒被插入格栅中,同时保持机构(诸如形成在网格壁上的凹坑的弹力)是活动的。 在本发明的组装方法中,首先将小柱排除,然后将燃料棒插入网格中。 一旦组装牢固,所有燃料棒就位就位并牢固地固定在网格上,控制杆导管插入网格中,管道固定在相应的格栅上。 通过以上述顺序进行组装操作,防止了在常规方法中将管道固定到栅格上时发生的栅格的轻微移动。 根据本发明的方法生产的最终组件没有表面损伤,并且组件的整体质量优良。

    Fuel rod for light water reactor and method for manufacturing the same
    6.
    发明授权
    Fuel rod for light water reactor and method for manufacturing the same 失效
    轻水反应堆用燃料棒及其制造方法

    公开(公告)号:US6014418A

    公开(公告)日:2000-01-11

    申请号:US908694

    申请日:1997-08-08

    CPC classification number: G21C3/07 Y02E30/40 Y10T428/12806

    Abstract: A fuel rod for a light water reactor comprises a cladding tube which comprises a zirconium alloy having a composition including 0.6 to 2.0% by weight of Nb, 0.5 to 1.5% by weight of Sn, 0.05 to 0.3% by weight of Fe, and the balance being Zr and incidental impurities; uranium oxide fuel pellets packed in the cladding tube; and end plugs comprising a zirconium alloy and closing both ends of the cladding tube. The cladding tube is sealed by TIG welding with the end plugs. Grain boundaries in each heat affected zone of the cladding tube, which are adjacent to a bead formed by TIG welding, have structural compositions including 4 to 30% by weight of Nb, and 0.9 to 20% by weight of Fe.

    Abstract translation: 一种用于轻水反应器的燃料棒包括一个包层管,它包括一种锆合金,其组成包括Nb为0.6-2.0%,Sn为0.5-1.5%,Fe为0.05-0.3%,以及 余量为Zr和杂质; 包裹在包壳管内的氧化铀燃料颗粒; 以及包括锆合金并封闭包层管的两端的端塞。 包层管通过TIG焊接与端塞密封。 与通过TIG焊接形成的焊道相邻的包覆管的每个受热影响区域中的晶界具有包含4至30重量%的Nb和0.9至20重量%的Fe的结构组成。

    Apparatus for attaching key member to nuclear fuel assembly grid and
detaching same therefrom
    7.
    发明授权
    Apparatus for attaching key member to nuclear fuel assembly grid and detaching same therefrom 失效
    用于将关键构件附接到核燃料组件网格并将其从其分离的装置

    公开(公告)号:US5313507A

    公开(公告)日:1994-05-17

    申请号:US972370

    申请日:1992-11-05

    CPC classification number: G21C3/334 Y02E30/40

    Abstract: An apparatus for attaching a key member to a nuclear fuel assembly grid and detaching the same therefrom is disclosed. The apparatus includes a supply and recovery mechanism, an inserting and removing mechanism, and a rotating mechanism. The supply and recovery mechanism operates to supply the key member to a prescribed position adjacent to the grid and recover the same. The inserting and removing mechanism is disposed between the supply and recovery mechanism and the grid, and operates to insert the key member supplied from the supply and recovery mechanism into the grid and remove the key member from the grid to recover the same to the supply and recovery mechanism. The rotating mechanism is disposed adjacent to the inserting and removing mechanism, and operates to rotate the key member inserted in the grid in a prescribed direction about the longitudinal axis to attach the same to the grid and rotate the same in a direction opposite to the prescribed direction to detach the same from the grid.

    Abstract translation: 公开了一种用于将键构件附接到核燃料组件网格并将其从其分离的装置。 该装置包括供应和恢复机构,插入和移除机构以及旋转机构。 供应和恢复机构操作以将关键构件提供给与电网相邻的规定位置并恢复。 插入和移除机构设置在供应和恢复机构与电网之间,并操作以将从供应和恢复机构供应的钥匙件插入电网中,并将钥匙元件从电网中取出以将其恢复到电源和 恢复机制。 所述旋转机构设置在所述插入移除机构的附近,并且操作以使围绕所述纵向轴线的规定方向插入所述格栅中的所述键构件旋转,以将其附接到所述格栅并沿与所述规定的方向相反的方向旋转 方向从网格分离。

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