Method of and apparatus for the treatment of radioactive waste water
from nuclear power plants
    1.
    发明授权
    Method of and apparatus for the treatment of radioactive waste water from nuclear power plants 失效
    核电厂放射性废水处理方法及设备

    公开(公告)号:US4440673A

    公开(公告)日:1984-04-03

    申请号:US132084

    申请日:1980-03-20

    IPC分类号: G21F9/08 G21F9/14

    CPC分类号: G21F9/08

    摘要: A method of and an apparatus for the treatment of radioactive waste water from a nuclear electricity-generating power plant. The radioactive waste water containing soluble solids, usually boric acid, is concentrated by evaporation according to the invention to a solids concentration above that which will form a saturated solution at room temperature, whereupon the resulting concentrate is introduced into a storage vessel and cooled therein to room temperature. Solids precipitate and sediment in this vessel and water is decanted from the sediment and recycled to the evaporator where the process is repeated. The process allows the amount of waste in terms of the original material treated which must be stored for a given prolonged period, say between one half and three quarters of a year, for radioactive decay prior to packaging of the waste to be significantly reduced by comparison with earlier systems.

    摘要翻译: 一种用于处理核发电厂放射性废水的方法和装置。 含有可溶性固体(通常为硼酸)的放射性废水通过根据本发明的蒸发浓缩至高于在室温下形成饱和溶液的固体浓度,由此将所得浓缩物引入储存容器中并冷却至 室内温度。 固体在该容器中沉淀并沉淀,并将水从沉淀物中倾出并再循环至蒸发器,在此处重复该过程。 该过程允许在处理废物的废物数量之前,必须在给定的较长时间(例如一年半至四分之三之间)之间存放放射性衰变,以便在废物包装之前通过比较显着减少放射性衰减 与早期的系统。

    Method of recovering boric acid from waste-water concentrates of nuclear
plants
    3.
    发明授权
    Method of recovering boric acid from waste-water concentrates of nuclear plants 失效
    从核废料浓缩水中回收硼酸的方法

    公开(公告)号:US4435184A

    公开(公告)日:1984-03-06

    申请号:US259094

    申请日:1981-04-30

    IPC分类号: C01B35/10 G21F9/06 B01D9/02

    摘要: A waste-water concentrate containing boric acid together with chemical residues and radionuclides, especially from a nuclear power plant, is treated to recovering boric acid which can be recycled to the plant. According to the invention, the practically neutral solution is acidified with an acid selected from the group which consists of sulfuric acid, hydrochloric acid, nitric acid and acetic acid to precipitate the boric acid which is separated from the concentrate and subjected to at least one recrystallization step. The boric acid thus obtained is of comparatively high purity.

    摘要翻译: 处理含有硼酸的废水浓缩物以及化学残留物和放射性核素,特别是来自核电厂的废水,以回收可回收到工厂的硼酸。 根据本发明,实际中性溶液用选自由硫酸,盐酸,硝酸和乙酸组成的组中的酸酸化以沉淀与浓缩物分离的硼酸,并进行至少一次再结晶 步。 由此获得的硼酸具有相当高的纯度。

    Method of and an apparatus for the evaluation of burned-out nuclear fuel
elements
    4.
    发明授权
    Method of and an apparatus for the evaluation of burned-out nuclear fuel elements 失效
    燃烧核燃料元素评估方法和装置

    公开(公告)号:US4382906A

    公开(公告)日:1983-05-10

    申请号:US174171

    申请日:1980-07-31

    IPC分类号: G21C17/07 G21C17/00

    CPC分类号: G21C17/07

    摘要: Nuclear fuel elements or slugs are removed from the nuclear reactor cores and subjected to inspection, according to the invention, by introducing a plurality of such elements into a submerged inspection vessel which is then closed, the liquid driven out by compressed air and deionized water (deionate) circulated through the inspection vessel at a constant rate. A portion of the deionized water is branched from the circulating stream at a constant rate and the activity of at least one fission-product nuclide is determined continuously to plot the activity versus temperature, thereby signaling a possible defect in the shell of a fuel element. In addition, ultrasonic vibration is applied in the inspection vessel to the fuel elements so that deposits on the exterior thereof are released into the deionate whose circulating path includes a filter and an ion-exchange column for removal of such deposits.

    摘要翻译: 根据本发明,将核燃料元件或s塞从核反应堆堆芯中取出并进行检查,通过将多个这样的元件引入浸没的检查容器中,然后将其关闭,液体由压缩空气和去离子水( 爱好者)以恒定的速率循环通过检验船。 去离子水的一部分以恒定速率从循环流中分支,连续测定至少一个裂变产物核素的活性以绘制活性与温度的关系,从而发出燃料元件外壳中的可能缺陷。 此外,在检查容器中将超声波振动施加到燃料元件,使得其外部的沉积物被释放到循环路径包括过滤器和用于除去这些沉积物的离子交换柱的酸性物质中。