System for backcooling radioactive-waste containers
    1.
    发明授权
    System for backcooling radioactive-waste containers 失效
    背冷放射性废物容器系统

    公开(公告)号:US5740215A

    公开(公告)日:1998-04-14

    申请号:US805407

    申请日:1997-02-24

    IPC分类号: G21C19/08 G21F5/10

    摘要: A transport/storage container holding spent radioactive fuel elements is cooled by withdrawing gases from inside the container to create a subatmospheric pressure therein, feeding coolant water from a reservoir into the container, withdrawing steam from the container, and condensing the steam outside the container into condensate water. A common pump is used both to withdraw gases and steam from the container. The steam is condensed by contacting it with water drawn from the reservoir. In addition the water drawn from the reservoir is passed countercurrent to the steam in a condenser and the condensate water is fed back to the reservoir.

    摘要翻译: 容纳废放射性燃料元件的运输/储存容器通过从容器内部排出气体而冷却,以在其中产生低于大气压的压力,将冷却水从储存器供给到容器中,从容器中取出蒸汽,并将容器外部的蒸汽冷凝成 冷凝水。 普通的泵既用于从容器中取出气体和蒸汽。 蒸汽通过与从储存器抽出的水接触而被冷凝。 此外,从储存器抽出的水与冷凝器中的蒸汽逆流通过,并将冷凝水反馈回储存器。

    Storage/transport container for radioactive material
    2.
    发明授权
    Storage/transport container for radioactive material 失效
    放射性物质的储存/运输容器

    公开(公告)号:US06498826B2

    公开(公告)日:2002-12-24

    申请号:US09728603

    申请日:2000-12-01

    IPC分类号: G21C1907

    摘要: A storage/transport container for radioactive material has a metallic outer shell, a metallic inner shell concentrically received in the outer cell and defining therewith an annular space, and an annular and continuous heat-conductive meander strip in the space. The strip is formed unitarily with a plurality of angularly spaced inner segments engaging the inner shell, respective angularly spaced outer segments engaging the outer shell, and respective generally radially extending webs extending between the inner and outer segments.

    摘要翻译: 用于放射性物质的储存/运输容器具有金属外壳,同心地容纳在外部单元中并且限定有外部空间的金属内壳,以及在该空间中的环形且连续的导热弯曲带。 条带与多个与内壳接合的有角度间隔开的内部分段形成为一体,与外壳相啮合的相应的角度间隔开的外部分段以及在内部和外部段之间延伸的相应的大致径向延伸的腹板。

    Lifting lug for nuclear-waste container
    4.
    发明授权
    Lifting lug for nuclear-waste container 失效
    核废料容器吊装

    公开(公告)号:US06724853B2

    公开(公告)日:2004-04-20

    申请号:US10278002

    申请日:2002-10-22

    IPC分类号: G21F506

    摘要: A lifting lug for a nuclear-waste container has a tubular body having an inner end formed with a flange adapted to be bolted to the container and a transverse wall set in and tightly fitted to a smaller-diameter outer end of the tubular body. The wall is a separate piece from the body and is press-fitted to the tubular body. The wall is mounted at a load point of the lifting lug. In addition the wall is formed of a disk and/or a ring, typically as one unitary piece with the disk and ring spaced from each other.

    摘要翻译: 用于核废料容器的吊耳具有管状体,其内端形成有适于螺栓连接到容器的凸缘,以及横向壁,其设置并紧密地配合到管状体的较小直径的外端。 墙体是与身体分离的一部分,并被压配合到管状体上。 墙壁安装在吊耳的负载点。 此外,壁由盘和/或环形成,通常为一个整体,其中盘和环彼此间隔开。

    Making storage/transport container for radioactive material

    公开(公告)号:US06438190B1

    公开(公告)日:2002-08-20

    申请号:US09728604

    申请日:2000-12-01

    IPC分类号: G21C1900

    摘要: A storage/transport container for radioactive material is made by first subdividing a chamber formed between an inner shell and an outer shell into first and second compartments by means of a foraminous partition having a predetermined maximum mesh size. Then an aggregate of a predetermined minimum particle size greater than the predetermined maximum mesh size is introduced into one of the compartments and a suspension of cement and water is introduced into the first compartment such that the aggregate remains in the one compartment and the cement and water flow through the partition into the second compartment. Normally the aggregate and the suspension are both introduced into the same compartment.

    Storage/transport container for spent nuclear-fuel elements
    6.
    发明授权
    Storage/transport container for spent nuclear-fuel elements 失效
    废核燃料元件的储存/运输集装箱

    公开(公告)号:US06389093B1

    公开(公告)日:2002-05-14

    申请号:US09596421

    申请日:2000-06-19

    IPC分类号: G21C1907

    摘要: A transport/storage container for spent nuclear-fuel elements has spaced inner and outer side walls defining an annular space extending along an axis, a cover at one end of the side walls, a floor at an opposite end of the side walls, and a plurality of heat-conducting elements in the space and each having one edge fixed, for instance by welding or bolting, to one of the side walls and an opposite edge bearing radially elastically on the other of the side walls.

    摘要翻译: 用于废核燃料元件的运输/储存容器具有间隔的内侧壁和外侧壁,其限定沿轴线延伸的环形空间,侧壁一端处的盖,侧壁的相对端的底板,以及 多个导热元件在空间中,并且每个具有一个边缘,例如通过焊接或螺栓连接固定到一个侧壁和在另一个侧壁上径向弹性地支承的相对边缘。