摘要:
Process for obtaining fritted oxide pellets of the MxOy type for nuclear fuels from solutions of soluble salts of the element or elements M, involving stage of precipitating the elements M by hydrogen peroxide in an acid medium. During this precipitation, there is an instantaneous dispersion of one of the reagents (solution of salts or peroxide) in the other, in order to obtain a homogenous mixture and an also instantaneous precipitation of the nuclei in a continuous liquid phase confined in an enclosure having minimum dimensions, the mother liquors being rapidly exhausted. The process makes it possible to obtain sintered pellets whose density exceeds 96% of the theoretical density.
摘要:
A process for the recovery of uranium which has been extracted from phosphate-bearing solutions by means of an organic solvent and which is re-extracted from said solvent by means of hydrofluoric acid is disclosed.The process is characterized in that sodium ions are introduced into the solution of hydrofluoric acid, while aluminum and magnesium ions may also be added to the sodium ions. That solution may be produced by recycling of a fraction of the suspension of fluoride from the re-extraction step, after having separated the solvent, and to which a make-up of sodium, aluminum and magnesium ions and hydrofluoric acid was added.
摘要:
A process for the recovery of the uranium present in phosphoric acid produced by a wet process in (A) by means of a suitable solvent (L.sub.9), which is carried out after separation of the gypsum in (B) formed in the attack operation, and elimination of the solid materials which are still in suspension, characterized in that, in order to avoid the formation of dross in the course of the operation of extracting the uranium which is previously reduced in (D), the step of eliminating the solid materials which are still in suspension is effected by a final solid-liquid separation operation in (C) and/or in (E), prior to extraction of the uranium in (F), in the presence of an added fraction of gypsum (S.sub.22) and/or (S.sub.23) resulting from the production of H.sub.3 PO.sub.4.
摘要:
A method of obtaining pellets of MxOy oxide, where M represents one or more elements used to make nuclear fuel pellets, as a means of obtaining very high density fritted pellets directly, i.e. without the intermediate powders being conditioned, comprising starting with a solution of soluble salts of the M elements, and treating them with hydrogen peroxide with the pH kept at from 2 to 2.5, in a continuous fluidized bed reactor comprising at least 3 superposed cylindrical sections of different diameters, the solutions in the central section being agitated vigorously, to obtain a precipitate which is subsequently calcined reduced, pressed then fritted.
摘要翻译:获得M x O y氧化物颗粒的方法,其中M表示用于制造核燃料颗粒的一种或多种元素,作为直接获得非常高密度烧结颗粒的方法,即不调节中间体粉末,包括从可溶性溶液 在含有至少3个重叠的不同直径的圆柱形切片的连续流化床反应器中,将pH值保持在2至2.5的过氧化氢处理它们,并将中心部分的溶液剧烈搅拌,至 得到沉淀,随后煅烧还原,然后烧结。
摘要:
The present invention relates to a process for the selective separation of uranium and molybdenum which are contained in an extract resulting from an amino solvent liquid-liquid extraction of a solution resulting from an attack on a molybdo-uraniferous ore by means of sulphuric acid, and which comprises re-extraction of the uranium in the presence of an oxidizing agent by means of an acid solution of an alkali metal chloride, followed by re-extraction of the molybdenum by means of an alkali metal carbonate solution. This process is characterized by using an oxidizing agent such as hydrogen peroxide, a small amount of which is added to the acid alkali metal chloride solution before the latter is brought into contact with the extract. This makes it possible to achieve selective separation of the uranium and molybdenum. This process can be used wherever molybdo-uraniferous ores are treated and where there is a requirement to produce a uranium concentrate which complies with the limits set in regard to the molybdenum content.
摘要:
A process for separating by means of an organic agent the uranium and the molybdenum contained in an aqueous liquor originating from a sulphuric attack of an urano-molybdeniferous ore which involves placing the said attacking liquor in contact with an organic extraction solution containing at least one tertiary or secondary amine in an (amine)/(Mo) molar ratio of up to 0.8, separating the molybdenum-charged organic phase from the uranium-rich aqueous phase, treating the organic phase with an aqueous liquor containing at least one mineral agent in the form of alkaline and ammonium hydroxide and/or carbonates to form an aqueous solution which is concentrated in molybdate.
摘要:
A method for removing ruthenium from a uranium-containing solution comprising adding a nitrite to the solution and passing the solution over a quaternary ammonium or tertiary amine resin to selectively fix the ruthenium.
摘要:
A process for making into useful products the uranium and rare earths contained in impure uranium tetrafluoride resulting from the recovery of uranium from phosphoric acid, comprising dissolving it in a hot condition in a nitric medium in the presence of an aluminum compound, treating the resulting solution with a solvent for extracting uranyl nitrate, which contains a phosphoric ester, and separating from the aqueous phase from which the uranium is removed, the solvent which is charged with uranyl nitrate to be made into a useful product, which provides that, in order to achieve easy separation of the aqueous phase from which the uranium has been removed, from the uranyl nitrate extraction solvent:(a) The operation of dissolution of UF.sub.4 is carried out in two steps at a suitable temperature, the first step comprising introducing insufficient amounts of nitric acid and the aluminum compound for complete dissolution of the impure uranium tetrafluoride and keeping the resulting suspension in an agitated condition for a period of time of at least 0.5 hour, and the second step comprising introducing amounts of nitric acid and the aluminum compound, which are at least sufficient to put into solution the uranium which was not dissolved in the first step, and while maintaining the suspension in an agitated condition; and(b) the uranyl nitrate is extracted by bringing into contact the aqueous medium resulting from the dissolution of UF.sub.4 and the uranyl nitrate extraction solvent containing the phosphoric ester.
摘要:
A process for extracting the uranium contained in phosphoric acid solutions by means of an extracting agent comprising an alkylpyrophosphoric acid, which comprises bringing into contact, in an agitated condition, the inorganic, phosphoric acid phase and an organic phase containing the extracting agent, thereby producing an emulsion, which is characterized in that, in an extraction unit comprising n stages in a cascade configuration, for each extraction stage, the emulsion is produced in a first step by simultaneously subjecting the two phases for a period of time T.sub.1 to an intense mechanical shearing action corresponding to a shearing coefficient of at least 5000 seconds.sup.-1 in order to multiply the contact surfaces for contact between said two phases, and then said emulsion in a second step is abruptly broke in a time T.sub.2, the sum of the times required for carrying out the two steps being at most 20 minutes.
摘要:
Processes for treating nitric effluents from plants so that a non-polluting stream is obtained and nitric values are recovered, which processes comprise acidifying nitric effluent, liquid-liquid extraction of the acidified effluent with an extraction agent comprising a neutral phosphoric ester and at least one long-chain alkylamine, and re-extraction of the loaded extraction agent with ammonia, thereby regenerating the extraction agent and providing ammonium nitrate, while at the same time providing a substantially nitric-free effluent.