利索-全球专利检索

  1. 登录
  2. 注册

搜索结果

130 条记录 (耗时 0.017 秒)

    Neutron Irradiated Material Repair
    1.
    发明申请
    Neutron Irradiated Material Repair 审中-公开
    中子照射材料修复

    公开(公告)号：US20160351281A1

    公开(公告)日：2016-12-01

    申请号：US14721834

    申请日：2015-05-26

    申请人： AREVA Inc.

    发明人： Jeffrey A. Enneking ,  Brian W. Ring

    IPC分类号： G21C21/18 ,  B23K26/144 ,  B23K26/36 ,  B23P6/00 ,  B23K26/342

    CPC分类号： B23K26/144 ,  B23K26/0884 ,  B23K26/1224 ,  B23K26/127 ,  B23K26/32 ,  B23K26/34 ,  B23K26/361 ,  B23K2101/12 ,  B23K2103/04 ,  B23K2103/26 ,  B23P6/00 ,  G21C13/087 ,  G21C19/02 ,  G21C19/20 ,  G21C21/00 ,  Y02E30/40

    摘要： The invention is a process of repairing cracked or microstructurally damaged portions of irradiated materials, such as nuclear reactor pressure vessels and shrouds. A damaged portion of the irradiated substrate is first removed, such as by electrical discharge machining (EDM). After removing the damaged portion, the recast layer inherent in the EDM process is then removed. Once the repair area substrate material has been removed to a calculated depth, the created cavity is then filled without releasing transmutated elements within the irradiated material. A chamber may be placed on the irradiated material surrounding the repair area to create an isolated work space.

    摘要翻译： 本发明是修复受辐射材料（例如核反应堆压力容器和护罩）的裂纹或微结构损坏部分的方法。 照射的基板的损坏部分首先被去除，例如通过放电加工（EDM）。 在去除损坏的部分之后，然后去除EDM工艺中固有的重铸层。 一旦修复区域基底材料已被去除到计算的深度，则所形成的空腔然后被填充而不释放被照射材料内的变形元素。 腔室可以被放置在围绕修复区域的辐射材料上以产生隔离的工作空间。

    Shield building
    5.
    发明申请
    Shield building 审中-公开
    盾建筑

    公开(公告)号：US20030215047A1

    公开(公告)日：2003-11-20

    申请号：US10422779

    申请日：2003-04-25

    申请人： Ishikawajima-Harima Heavy Industries Co., Ltd.

    发明人： Hiroe Kobayashi ,  Tatsuya Fujiwaka

    IPC分类号： G21C009/00

    CPC分类号： G21C13/087 ,  G21C13/00 ,  Y02E30/40

    摘要： A shield building peripherally surrounds a containment vessel 3 and has an outer wall 9 with air inlets 4 adjacent to an upper end of the outer wall, a roof 10 contiguous with the upper end of the outer wall 9 having a central opening 12 and an inner wall 11 extending downward from a lower surface of the roof 10 adjacent to a peripheral edge of the roof and facing via gaps 13 and 14 to inner and outer peripheries of the outer wall 9 and containment vessel 3, respectively. The outer and inner walls 9 and 11 and the roof 10 are integrally provided by a steel structure to attain simplification in structure and reduction in quantity of the shield building.

    摘要翻译： 屏蔽建筑外围围绕容纳容器3并且具有外壁9，外壁9具有与外壁的上端相邻的空气入口4，与外壁9的上端邻接的屋顶10具有中心开口12和内壁 壁11从屋顶10的下表面向下延伸，邻近屋顶的周边边缘并且经由间隙13和14分别面向外壁9和容纳容器3的内周和外周。 外壁9和内壁11以及屋顶10由钢结构一体地提供，以实现盾构结构的结构简化和数量减少。

    Method of and apparatus for checking the degradation of a pressure vessel of a nuclear reactor
    7.
    发明授权
    Method of and apparatus for checking the degradation of a pressure vessel of a nuclear reactor 失效
    用于检查核反应堆压力容器退化的方法和装置

    公开(公告)号：US5687204A

    公开(公告)日：1997-11-11

    申请号：US319629

    申请日：1994-10-07

    申请人： Katsuyuki Ara ,  Nobuya Nakajima ,  Noriya Ebine

    发明人： Katsuyuki Ara ,  Nobuya Nakajima ,  Noriya Ebine

    IPC分类号： G21C13/087 ,  G21C17/003 ,  G21C17/00

    CPC分类号： G21C13/087 ,  G21C17/003 ,  G21Y2002/102 ,  G21Y2002/204 ,  Y02E30/40

    摘要： In a method of and an apparatus for checking the degradation of the pressure vessel of a nuclear reactor with the pressure vessel of the nuclear reactor being directly measured in a non-destructive manner, a magnetic yoke having an exciting coil and a magnetic flux measuring coil is closely placed in contact with the inner wall of the pressure vessel of the nuclear reactor. The hysteresis magnetization characteristics of the closed magnetic path formed by the magnetic yoke and the pressure vessel of the nuclear reactor are measured. The coercive forces are obtained by the hysteresis characteristics. The hardness of the material comprising the pressure vessel of the nuclear reactor at the part of the magnetic path formed in the pressure vessel of the nuclear reactor is obtained from the coercive forces and the degradation of the material comprising the pressure vessel is checked from the hardness.

    摘要翻译： 在以非破坏性方式直接测量核反应堆的压力容器的核反应堆的压力容器的劣化检测方法和装置中，具有励磁线圈和磁通量测量线圈的磁轭 紧密地与核反应堆的压力容器的内壁接触。 测量由磁轭和核反应堆的压力容器形成的闭合磁路的磁滞特性。 矫顽力通过滞后特性得到。 由核反应堆的压力容器中形成的磁路部分的核反应堆的压力容器的材料的硬度是由矫顽力获得的，并且从包含压力容器的材料的劣化可以从硬度 。

    Heating equipment installation system
    9.
    发明授权
    Heating equipment installation system 失效
    加热设备安装系统

    公开(公告)号：US5040287A

    公开(公告)日：1991-08-20

    申请号：US368495

    申请日：1989-06-19

    申请人： Robert E. Meuschke ,  Paul P. Pomaibo

    发明人： Robert E. Meuschke ,  Paul P. Pomaibo

    IPC分类号： G21C13/00 ,  C21D1/26 ,  C21D9/00 ,  G21C13/087

    CPC分类号： G21C13/087 ,  C21D9/0068 ,  Y02E30/40 ,  Y10T29/531 ,  Y10T29/53974 ,  Y10T29/53983

    摘要： A method for installing a heater unit assembly (52, 54) in a reactor pressure vessel (2) for performance of an annealing treatment on the vessel (2), the vessel (2) having a vertical axis, being open at the top, being provided at the top with a flange (6) having a horizontal surface, and being provided internally, at a location below the flange (6), with orientation elements (8) which are asymmetrical with respect to the vertical axis, by the steps of:providing an orientation fixture (10) having an upwardly extending guide member (18) and orientation elements (14, 16) and installing the orientation fixture (10) in the vessel (2) so that the orientation elements (14,16) of the orientation fixture (10) mate with the orientation elements (8) of the pressure vessel (2) in order to establish a defined position of the orientation fixture (10) in the pressure vessel (2), and so that the guide member (18) projects above the pressure vessel (2) flange (6);placing a seal ring (30) in a defined position on the pressure vessel (2) flange (6) with the aid of the guide member (18);mounting at least one vertical, upwardly extending guide stud (40) upon the seal ring (30);withdrawing the orientation fixture (10) from the pressure vessel (2); andmoving the heater unit assembly (52,54) vertically downwardly into the pressure vessel (2) while guiding the heater unit assembly (52,54) along a path with the aid of the guide stud (40).