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Process for the processing of irradiated reactor fuel 12-40 times higher substances

机译:辐照反应堆燃料的处理工艺是高出12至40倍的物质

摘要

An aqueous solution of irradiated nuclear fuel is subjected to a single cycle extraction with an organic solvent and then the organic phase is contacted with an aqueous extraction agent to produce an aqueous extract stream containing uranium and at least one of the fission products ruthenium, zirconium and niobium, the aqueous stream is dehydrated, the solid residue fluorinated, and uranium fluoride separated from fission product fluoride. In a process described with reference to a flow diagram, uranium dioxide fuel elements are dissolved in nitric acid and the solution is introduced at about the middle of an extraction column where it flows downwards in countercurrent with diethoxybutane or dimethoxypentane; a stripping nitric acid solution is fed into the top of the column. The organic solvent extracts uranium, plutonium, and some of the fission products specified above, leaving the rest of the fission products in the aqueous phase which is evaporated and calcined, nitric acid being recovered. The organic phase is contacted in a second column with a nitric acid solution containing ferrous iron, which reduces and extracts the plutonium. The organic phase from the second column contains uranium and the specified fission products, all of which are returned to aqueous solution by contact in a third column with very dilute nitric acid. The solvent from this column is purified by distillation and used again for extraction; the aqueous solution is evaporated, the residue calcined and treated with HF at 250-350 DEG C. and with F2 at 300-600 DEG C. to form volatile fluorides. The vapours are passed through a partial condenser and a separator, where fission product fluorides are removed, leaving a stream of pure UF6. Alternatively fluorination may take place with F2 alone, and separation of the fluorides may be effected by fractional distillation. In a modified process, the organic solvent is a solution of tributyl phosphate in kerosene, which is purified by extraction with aqueous sodium carbonate solution. Other organic solvents referred to are methyl isobutyl ketone, dibutyl carbitol, and amines.
机译:将辐照过的核燃料的水溶液用有机溶剂进行单循环萃取,然后使有机相与含水萃取剂接触,以产生含有铀和裂变产物钌,锆和至少一种裂变产物的含水萃取物流。铌,将水流脱水,将固体残留物氟化,从裂变产物氟化物中分离出氟化铀。在参照流程图描述的方法中,将二氧化铀燃料元件溶解在硝酸中,并将溶液引入萃取塔的中间,在该塔中与二乙氧基丁烷或二甲氧基戊烷逆流向下流动。汽提硝酸溶液被送入塔顶。有机溶剂萃取铀,p和上述某些裂变产物,将其余裂变产物留在水相中,将其蒸发并煅烧,回收硝酸。有机相在第二塔中与含有亚铁的硝酸溶液接触,亚铁还原和萃取the。来自第二个塔的有机相包含铀和特定的裂变产物,所有这些都通过在第三个塔中与非常稀的硝酸接触而返回水溶液。来自该塔的溶剂通过蒸馏进行纯化,并再次用于萃取。蒸发水溶液,将残余物煅烧并在250-350℃下用HF和在300-600℃下用F 2处理以形成挥发性氟化物。蒸气通过部分冷凝器和分离器,在其中分离出裂变产物氟化物,剩下纯UF6物流。可选择地,氟化作用可以单独用F 2进行,并且氟化物的分离可以通过分馏进行。在改进的方法中,有机溶剂是磷酸三丁酯在煤油中的溶液,将其通过用碳酸钠水溶液萃取进行纯化。提及的其他有机溶剂是甲基异丁基酮,二丁基卡必醇和胺。

著录项

  • 公开/公告号DE1184745B

    专利类型

  • 公开/公告日1965-01-07

    原文格式PDF

  • 申请/专利权人 GEN ELECTRIC;

    申请/专利号DE1963G038307

  • 发明设计人 ANDERSON CLEVE RICHARD;

    申请日1963-07-26

  • 分类号C01G43/06;C22B60/02;C22B60/04;G21C19/46;

  • 国家 DE

  • 入库时间 2022-08-23 15:53:05

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