Irradiated fuel recovery system
    4.
    发明授权
    Irradiated fuel recovery system 失效
    IRRADIATED燃料回收系统

    公开(公告)号:US3714324A

    公开(公告)日:1973-01-30

    申请号:US3714324D

    申请日:1968-06-18

    申请人: GEN ELECTRIC

    发明人: WEECH M

    摘要: An improved process for recovering irradiated nuclear reactor fuel material is disclosed. This process includes the steps of extracting uranium, plutonium and neptunium from a solution of irradiated fuel, passing this stream to a reflux column, where a high saturation of uranium is maintained. Separation of uranium from plutonium and neptunium, and further decontamination of uranium results from this high saturation. This process is simple, has a high recovery efficiency and high decontamination, uses relatively small amounts of process reagents and produces a relatively small volume of radioactive waste material.

    摘要翻译: 公开了一种用于回收辐照的核反应堆燃料材料的改进方法。 该方法包括从辐照燃料溶液中提取铀,钚和the the的步骤,将该物流送入回流塔,在那里保持铀饱和度高。 从钚和分离铀,进一步净化铀会导致这种高饱和度。 该方法简单,具有高回收效率和高去污性,使用相对少量的加工试剂,并产生较小体积的放射性废料。