公开(公告)号：US4262517A

公开(公告)日：1981-04-21

申请号：US63449

申请日：1979-08-03

申请人： Hideaki Kamohara ,  Yuji Yoshitomi ,  Takaichi Koyama ,  Yasumasa Tamai

发明人： Hideaki Kamohara ,  Yuji Yoshitomi ,  Takaichi Koyama ,  Yasumasa Tamai

IPC分类号： B21D19/00 ,  B21D1/08 ,  B21D3/14 ,  B21D22/10 ,  B21D47/02 ,  B21C3/12

CPC分类号： B21D1/08 ,  B21D22/105

摘要： In a method of correcting a distorted pipe end to an original substantially true circular cross-section, external loads are applied to the outer peripheral surface of the pipe adjacent to the end thereof to forcibly deform the pipe end to the substantially true circular cross-section. The external loads are maintained to keep this substantially true circular cross-sectional shape while an internal pressure is applied to the inner peripheral surface of the pipe end until a circumferential stress produced in the pipe reaches an amount which exceeds the yield stress of the pipe to give a radial permanent deformation to the pipe for thereby producing a circumferentially uniformly distributed residual stress in the pipe.

摘要翻译： 在将变形的管端校正为原始基本上真实的圆形横截面的方法中，外部负载施加到邻近管的端部的管的外周表面，以将管端强制变形为基本上真实的圆形横截面 。 保持外部负载以保持这个基本上真实的圆形横截面形状，同时内管施加到管端的内周面，直到管道产生的周向应力达到超过管的屈服应力的量 对管道产生径向永久变形，从而在管道中产生周向均匀分布的残余应力。

公开(公告)号：US4440339A

公开(公告)日：1984-04-03

申请号：US272882

申请日：1981-06-12

申请人： Yasumasa Tamai ,  Takaichi Koyama

发明人： Yasumasa Tamai ,  Takaichi Koyama

IPC分类号： G21C7/16 ,  F16L41/00 ,  G21C7/10 ,  G21C13/036 ,  B23K31/06

CPC分类号： G21C7/10 ,  G21C13/036 ,  G21Y2002/402 ,  G21Y2002/501 ,  G21Y2004/50 ,  G21Y2004/501 ,  G21Y2004/504 ,  Y02E30/39

摘要： A method of repairing the housing of a control rod driving system of a nuclear reactor, the housing being inserted through the wall of a pressure vessel of the reactor into a cylindrical sleeve secured to the inner surface of the vessel, which housing is jointed by welding to the cylindrical sleeve. The method comprises the steps of: cutting the housing in the circumferential direction of the housing at a position defined between the weld joint and the inner surface of the reactor vessel and surrounded by the cylindrical sleeve, thereby to divide the housing into a first housing part still attaching to the weld joint and another removable housing part; removing the removable other housing part; inserting a second housing part into said cylindrical sleeve through the wall of the nuclear reactor vessel; and uniting the first housing part and the second housing part by welding thereby to form a new housing for the control rod driving system.

摘要翻译： 一种修复核反应堆的控制杆驱动系统的壳体的方法，该壳体通过反应器的压力容器的壁插入固定到容器的内表面的圆柱形套筒中，该壳体通过焊接而接合 到圆柱形套筒。 该方法包括以下步骤：在壳体的圆周方向上在限定在焊接接头和反应堆容器的内表面之间的位置处切割壳体并被圆柱形套筒包围，从而将壳体分成第一壳体部分 仍然附接到焊接接头和另一个可移除的壳体部分; 移除可拆卸的其他外壳部件; 通过核反应堆容器的壁将第二壳体部件插入到所述圆柱形套筒中; 并且通过焊接使第一壳体部分和第二壳体部分结合从而形成用于控制杆驱动系统的新壳体。

公开(公告)号：US4311556A

公开(公告)日：1982-01-19

申请号：US58431

申请日：1979-07-18

申请人： Taro Iwamoto ,  Shimon Ando ,  Sho Kusumoto ,  Tsutomu Omae ,  Toshitaka Suzuki ,  Masatake Takidera ,  Takaichi Koyama ,  Kunio Hamada ,  Kazuhiro Yoshida

发明人： Taro Iwamoto ,  Shimon Ando ,  Sho Kusumoto ,  Tsutomu Omae ,  Toshitaka Suzuki ,  Masatake Takidera ,  Takaichi Koyama ,  Kunio Hamada ,  Kazuhiro Yoshida

IPC分类号： G01N29/04 ,  B25J9/04 ,  G01N21/91 ,  G01N29/24 ,  G21C17/003 ,  G21C17/01 ,  G21C17/00

CPC分类号： G21C17/01 ,  B25J9/041

摘要： In a method and a system for inspection of the inside of a nuclear reactor vessel in which an inspection device for inspecting a defect in a nuclear reactor vessel is so moved by a drive/control device as to permit inspection of a part to be inspected in the reactor vessel, and the presence or absence of defect in the reactor vessel is judged based upon information from the inspection device in the course of the above-mentioned movement of the inspection device; the movement of the inspection device is pursued and monitored by monitor means, and the movement of the inspection device is suppressed when an abnormality in the movement of the inspection device is judged based upon information from the monitor means, to avoid the abnormal movement.

摘要翻译： 在用于检查核反应堆容器内部的方法和系统中，其中用于检查核反应堆容器中的缺陷的检查装置被驱动/控制装置移动以允许检查待检查部件 在上述检查装置的移动过程中，根据来自检查装置的信息来判断反应堆容器中是否存在缺陷; 检查装置的移动由监视装置追踪和监视，并且当根据来自监视装置的信息来判断检查装置的移动异常时，检查装置的移动被抑制，以避免异常移动。

公开(公告)号：US4144992A

公开(公告)日：1979-03-20

申请号：US829891

申请日：1977-09-01

申请人： Tsutomu Omae ,  Takanori Shibata ,  Keiziro Sakai ,  Tomio Iizuka ,  Takaichi Koyama

发明人： Tsutomu Omae ,  Takanori Shibata ,  Keiziro Sakai ,  Tomio Iizuka ,  Takaichi Koyama

IPC分类号： B23K9/10 ,  B23K9/028

CPC分类号： B23K9/0286

摘要： Method for controlling an automatic pipe welder is disclosed. In the automatic welder which requires remote control, welding conditions for butt welding pipes are stored and an actual joint geometry or groove shape is sensed. From signals relating to the stored welding conditions and the sensed groove shape, a control command signal in actual welding is produced to effect welding under an optimum condition. On the other hand, an arc condition at an actual welding point and a melting condition of a metal are monitored and displayed to modify the welding conditions in accordance with the monitored condition to control the automatic pipe welder.

摘要翻译： 公开了一种用于控制自动管焊机的方法。 在需要远程控制的自动焊机中，存储对接焊管的焊接条件，并且感测到实际的接头几何形状或槽形状。 从存储的焊接条件和感测到的槽形状的信号中，产生实际焊接中的控制指令信号，以在最佳条件下进行焊接。 另一方面，对实际焊接点处的电弧状态和金属的熔化条件进行监视和显示，以根据监视条件修改焊接条件以控制自动焊接机。