摘要:
A process for obtaining molybdenum as a useful product from aqueous solutions to be purified, according to claim 1 of French patent No. 2 404 601, which contain, besides said molybdenum, alkali metal carbonate, sulphate, hydroxide or hydrogen carbonate and which may also contain uranium, and inorganic and/or organic impurities, said solutions being treated at a temperature which is at most equal to the boiling temperature by means of lime to convert the alkali metal carbonate into hydroxide and to precipitate the insoluble calcium salts formed, then separating and washing the first precipitate which essentially contains calcium carbonate, from an alkali metal hydroxide-enriched liquor, which is concentrated by evaporation at the same time as the washing liquor of the first precipitate, to produce an alkali metal hydroxide content which is at most equal to 50%, to produce a second precipitate formed by a mixture of alkali metal molybdate and sulphate, characterized in that said solid mixture is dispersed in an acid aqueous liquor which is heated at from 120.degree. C. to 250.degree. C. under pressure to cause precipitation of anhydrous Mo0.sub.3 which is subsequently separated from the mother liquor which essentially contains alkali metal sulphate.
摘要:
A method of dissolving impure uranium tetrafluoride in a hot state in a nitric acid solution in the presence of an aluminum compound. For the purpose of obtaining a uranyl nitrate solution which can easily be separated from the solid phase formed during treatment, the dissolving is carried out in two stages at an appropriate temperature. The first stage comprises introducing quantities of nitric acid and of the aluminum compound which are insufficient to dissolve the impure uranium tetrafluoride completely, and keeping the resultant suspension agitated for a period of at least 0.5 hour. The second stage comprises introducing quantities of nitric acid and of the aluminum compound which are at least sufficient to dissolve the uranium not dissolved in the first stage, while keeping the suspension agitated.
摘要:
A control rod having a center of thermal neutron absorbing material is provided specifically for use within the core of a nuclear reactor, extending through the central zone of maximum flux density. The center is formed of a plurality of portions, normally three, arranged end to end and defining joins therebetween. A central one of said portions extends continuously through the zone of maximum flux density with the joins located outward of this zone.
摘要:
A process for extracting arsenic from aqueous solution to be purified, in accordance with claim 1 of U.S. Pat. No. 2,404,601, which also contains alkali metal carbonate, sulphate, hydroxide or hydrogen carbonate, and which may also contain at least one of the metals vanadium, uranium and molybdenum, comprising caustification of said solutions by means of lime to convert the carbonates into alkali metal hydroxides, followed by separation of an alkali metal hydroxide-enriched liquor and a first precipitate essentially containing calcium carbonate which is subjected to a washing operation, concentration by evaporation of the mixture of the washing liquor of the first precipitate to produce a second precipitate which essentially comprises alkali metal sulphate, which is characterized in that, before the aqueous solution is caustified, the aqueous solution is treated by a magnesium compound in an amount at least equal to the stoichiometric amount required to cause precipitation of magnesium arsenate.
摘要:
A process for obtaining a dense ion-exchange anionic resin and the product so obtained. The resin is of the type based on a co-polymer of styrene and divinylbenzene. The process involves a liquid phase treatment comprising contacting the resin with bromide in a liquid phase and simultaneously charging the liquid phase with gaseous chlorine while in contact with the resin for reaction to provide a styrene divinylbenzene copolymer ion-exchange anionic resin containing bromine and chlorine groups.
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 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:
A process for extracting arsenic from aqueous solutions containing alkali metal carbonate, sulfate and hydroxide or hydrogen carbonate, at least one metal selected from the group consisting of vanadium, uranium and molybdenum in the form of an alkali metal salt, and inorganic and/or organic impurities, comprising the steps of caustifying the solution with lime to convert the alkali metal carbonates into hydroxides to precipitate the insoluble calcium salts formed, concentrating the solution by evaporation of the effluent liquids originating from the caustification step to obtain a precipitate substantially comprising alkali metal sulfate wherein the caustification is performed in two steps, consisting of (a) treating the solutions with an amount of lime approximately equal to but less than the stoichiometric amount necessary to convert the alkali metal carbonates into hydroxides as a first precipitate, and (b) after separating and washing the first precipitate, treating the resulting liquor with at least the stoichiometric amount of lime necessary to precipitate the arsenic in solution and the carbonate ions still present. The process is well adapted to the treatments of the liquors originating from the alkaline attack of uraniferous ore.