Method of radioactive offgas filtration and filter regeneration and
device for implementing the method
    1.
    发明授权
    Method of radioactive offgas filtration and filter regeneration and device for implementing the method 失效
    放射性废气过滤和过滤器再生方法及其实施方法

    公开(公告)号:US4264341A

    公开(公告)日:1981-04-28

    申请号:US923891

    申请日:1978-07-12

    IPC分类号: G21F9/02 B01D46/04

    CPC分类号: G21F9/02 Y10S55/09

    摘要: Method and device for effecting radioactive offgas filtration by means of a mass of filter material, and filter material regeneration, at temperatures in excess of 500.degree. C. in which substances to be filtered impinge on the filter material mass in at least one direction, filtration being effected by removing a layer of contaminated filter material in the direction opposed to the direction in which substances impinge on the filter material in order to remove the filtered substances for filter cleaning. Removal of the contaminated filter material is carried out by adding a fluxing agent to the filter material at operating temperatures for regenerating the filter material by means of a cleanup melt. This fluxing agent may be a glass frit, an alkali hydroxide or an alkali or alkaline earth metal salt.

    摘要翻译: 在超过500℃的温度下,通过大量过滤材料进行放射性废气过滤和过滤材料再生的方法和装置,其中待过滤的物质在至少一个方向上撞击在过滤材料上,过滤 通过在与物质撞击过滤材料的方向相反的方向上去除污染的过滤材料层以除去过滤物质以进行过滤器清洁来实现。 污染过滤材料的去除是通过在用于通过清理熔体再生过滤材料的操作温度下将助熔剂添加到过滤材料中来进行的。 该助熔剂可以是玻璃料,碱金属氢氧化物或碱金属或碱土金属盐。

    Method and apparatus for processing aqueous radioactive wastes for
noncontaminating and safe handling, transporting and final storage
    2.
    发明授权
    Method and apparatus for processing aqueous radioactive wastes for noncontaminating and safe handling, transporting and final storage 失效
    处理含水放射性废物用于不污染和安全处理,运输和最终储存的方法和装置

    公开(公告)号:US4144186A

    公开(公告)日:1979-03-13

    申请号:US775288

    申请日:1977-03-07

    CPC分类号: G21F9/14 G21F9/305

    摘要: A method for processing aqueous radioactive wastes for noncontaminating and safe handling, transport and final storage wherein nitric acid and/or nitrate containing aqueous radioactive waste solutions are continuously denitrated with formic acid, spray-dried and calcinated in a spray dryer having a spray nozzle surrounded by a reaction chamber, the resulting calcinate is mixed with glass former substances, the mixture is melted and the melt is caused to solidify into a glass, glass ceramic or glass ceramic-like block and the waste gases produced during denitration-drying and calcination are conducted through a filter system in order to remove solid particles that have been carried along by the gas. The process steps of denitration, drying and calcination are effected simultaneously and are terminated with the aid of and the intimate energy exchange in the fine distribute droplets superheated steam in the vicinity of the spray nozzle. The resulting waste gases are cleaned within a filter chamber surrounding the reaction chamber with the spray nozzle. An apparatus is provided for practicing the method.

    摘要翻译: 一种用于处理用于不污染和安全处理,运输和最终储存的含水放射性废物的方法,其中将硝酸和/或硝酸盐含有放射性废水的含水溶液用甲酸连续硝酸,喷雾干燥并在喷雾干燥器中煅烧,所述喷雾干燥器包括喷雾喷嘴 通过反应室,将所得的煅烧物与玻璃形成物混合,将混合物熔化并使熔体固化成玻璃,玻璃陶瓷或玻璃陶瓷状嵌段,并且在脱硝干燥和煅烧期间产生的废气为 通过过滤系统进行传导,以便去除已被气体携带的固体颗粒。 脱硝,干燥和煅烧的过程步骤同时进行,并借助于喷雾嘴附近的细分散液滴过热蒸汽中的紧密能量交换终止。 所产生的废气在具有喷嘴的反应室周围的过滤室内被清洁。 提供了一种用于实施该方法的装置。

    Method for noncontaminating solidification of radioactive waste materials
    3.
    发明授权
    Method for noncontaminating solidification of radioactive waste materials 失效
    放射性废料无污染固化方法

    公开(公告)号:US4202792A

    公开(公告)日:1980-05-13

    申请号:US862048

    申请日:1977-12-19

    CPC分类号: G21F9/305

    摘要: Method for the solidification, in a manner which protects the environment against contamination, of waste materials obtained during reprocessing of irradiated nuclear fuel and/or breeder materials in a matrix of borosilicate glass. Highly radioactive solutions or slurries containing the waste materials in dissolved or suspended form are evaporated in a vessel in the presence of glass former substances until they are dry, the dry residue is calcinated and the calcinate is melted together with the glass formers while the waste gases are discharged to the environment. The waste liquid is obtained from a reprocessing system without pretreatment, is mixed with glass formers and a reduction agent and then is introduced in a controlled, continuous manner into the center of a borosilicate glass melt disposed in a melting crucible at a temperature in the region of 1000.degree. to 1400.degree. C. to form an island-like drying and calcinating zone on the surface of the melt while avoiding contact of the waste liquid with the walls of the crucible. A reducing atmosphere is formed and the presence of components in the waste gas which would radiologically and/or chemically contaminate the environment are substantially avoided.

    摘要翻译: 以保护环境免受污染的方式固化在硼硅酸盐玻璃基质中辐照的核燃料和/或育种材料后处理过程中获得的废物的方法。 含有溶解或悬浮形式的废物的高放射性溶液或浆液在玻璃形成物质存在下在容器中蒸发直到它们干燥,干燥的残余物被煅烧,并且煅烧物与玻璃形成器一起熔化,而废气 被排放到环境中。 废液从未经预处理的后处理系统获得,与玻璃形成剂和还原剂混合,然后以受控的连续方式引入设置在熔化坩埚中的硼硅酸盐玻璃熔体的中心,该区域在该区域的温度 在1000〜1400℃下,在熔融物的表面形成岛状的干燥和煅烧区,同时避免废液与坩埚的壁接触。 形成还原气氛,并且基本上避免了在放射和/或化学上污染环境的废气中的组分的存在。