Method for removing radioactive plastic wastes and apparatus therefor
    2.
    发明授权
    Method for removing radioactive plastic wastes and apparatus therefor 失效
    去除放射性塑料废物的方法及其设备

    公开(公告)号:US4204974A

    公开(公告)日:1980-05-27

    申请号:US850369

    申请日:1977-11-10

    CPC分类号: G21F9/08 G21F9/008 G21F9/307

    摘要: Method and apparatus for encapsulating radioactive plastic wastes, particularly radioactively contaminated ion exchange filter material containing water, in bituminous solidification substances, by drying the radioactive waste separate and apart from the bituminous substance, introducing regulated amounts of dry radioactive waste into the bituminous substance and kneading the mixture at a temperature of 120.degree. C. or lower to encapsulate the dry radioactive waste by the mechanical action of the kneading, and pouring the kneaded, encapsulated radioactive plastic waste into a container. Undesired decomposition with discharge of pollutants into the atmosphere are avoided.

    摘要翻译: 将放射性塑料废物,特别是放射性污染的含水离子交换过滤材料包裹在沥青固化物质中的方法和装置,通过将放射性废物与沥青物质分开干燥,将规定量的干放射性废物引入沥青物质和揉捏 混合物在120℃或更低的温度下通过捏合的机械作用包封干燥的放射性废物,并将捏合的包封的放射性塑料废物倒入容器中。 避免了污染物排放到大气中的不希望的分解。

    Method and apparatus for processing aqueous radioactive wastes for
noncontaminating and safe handling, transporting and final storage
    4.
    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。

    Thermodynamically stable product for permanent storage and disposal of
highly radioactive liquid wastes
    7.
    发明授权
    Thermodynamically stable product for permanent storage and disposal of highly radioactive liquid wastes 失效
    用于永久储存和处置高放射性液体废物的热力学稳定产品

    公开(公告)号:US4097401A

    公开(公告)日:1978-06-27

    申请号:US627310

    申请日:1975-10-30

    CPC分类号: C03C10/0036 G21F9/305

    摘要: Highly radioactive liquid wastes are permanently stored in a solidification matrix containing the components of a known borosilicate glass together with nucleation agents selected from the group consisting of oxides of Li, K, Mg, Mo and Cr, fluorides of those metals and of Al, and pure noble metals in the elemental form with particles with sizes smaller than 0.1 .mu.m in diameter, and up to 35% by weight of waste fission and corrosion products or waste fission and corrosion products and gadolinium oxide. The product is produced by denitrating and calcining the radioactive waste solution, melting the calcined waste product together with a borosilicate frit containing nucleation agents at a temperature of between 1,050.degree. and 1,200.degree. C, and maintaining it in its melted state for 3 to 5 hours, subsequently cooling the resulting mixture until to a given temperature and maintaining it at this temperature for a given time period to permit nucleation to occur, then elevating the temperature of the mixture with an constant heating rate until to a given higher temperature, maintaining it at this higher temperature for about 24 hours, and finally cooling it with a constant cooling rate to ambient temperature.

    摘要翻译: 将高放射性液体废物永久地储存在含有已知硼硅酸盐玻璃的组分的固化基质中,以及选自Li,K,Mg,Mo和Cr的氧化物,这些金属和Al的氟化物和Al的成核剂,以及 元素形式的纯贵金属,直径小于0.1μm的颗粒,以及高达35%重量的废物裂变和腐蚀产物或废物裂变和腐蚀产物和氧化钆。 该产品通过脱硝和煅烧放射性废物溶液,将煅烧废弃物与含有成核剂的硼硅酸盐玻璃料在1050至1200℃之间的温度下熔化,并将其保持在其熔融状态3至5小时 ,随后将所得混合物冷却至一定温度,并将其在该温度下保持给定时间以允许发生成核,然后以恒定的加热速率将混合物的温度升高至给定的较高温度,将其保持在 这种较高的温度约24小时,最后以恒定的冷却速率冷却至环境温度。