Procedure for extraction of uranium
SUBSTANCE: procedure consists in production of sample containing uranium and silicon dioxide, in treatment of sample containing uranium and silicon dioxide and in production of material containing dissolved uranium and silicon dioxide. Also, material contains SiO2 over or equal to 100 mg/l. Further, dissolved uranium is extracted from material using at least one strong base anion-exchanging resin of macro-reticular structure. There is obtained uranium containing product in combination with strong-base anion-exchanging resin of macro-reticular structure. Further, uranium containing product is eluted and extracted from combination with strong-base anion-exchanging resin of macro-reticular structure.
EFFECT: increased efficiency of uranium extraction from mediums with high contents of silicon dioxide.
9 cl, 3 tbl, 1 ex
The present invention relates to the use of strongly basic anion-exchange resins macrostate patterns for the extraction of uranium in environments with high silicon dioxide content. The required method of application of ion exchange resins for uranium recovery in environments with high silicon dioxide content without concomitant contamination of ion exchange resins by silicon dioxide. Contamination of silicon dioxide leads to difficulties in the way of extraction of uranium, because it affects the kinetics of absorption and elution for anion-exchanger. The kinetics of absorption and elution is important because these characteristics are associated with economic efficiency and productivity of the technology to extract uranium as a whole.
One attempt to overcome problems associated with uranium extraction, described in the publication ..Haines' "The South African Programme on the Development of Continuous Fluidized Bed Ion Exchange with Specific Reference to its Application to the Recovery of Uranium." Although this publication describes the application of macromolecular ion-exchange resins for uranium recovery, weakly basic resin, described in the publication Haines, polluted due to the accumulation of silicon dioxide that must be removed using a separate time-consuming stage of separation. You need to make technology cleaning processing anion exchange resin is more economical. The situation considered in the us is oasam the invention, is to develop a way to extract uranium in environments with high silicon dioxide content using strongly basic anion-exchange resins macrostate patterns without the need for frequent and time-consuming cleaning processing of the resin, which is necessary for the technology described in the publication Haines.
Another attempt to develop the technology to extract uranium at high silicon dioxide content is the use of strong base gel type resins. Strong gel-like resin is exposed to pollution, and at the subsequent stages required laborious purification resin. This problem is solved by the present invention. At high silicon dioxide content, strongly basic anion-exchange resin macrostate patterns, such as proposed in this invention, are preferred, because they are observed acceptable kinetics of absorption and elution, acceptable consumption of NaOH, and stability performance of the resin in time, which is better than for strong base gel anion exchange resin at a lower silicon dioxide content.
The present invention relates to a method in which a strongly basic anion-exchange resin macrostate patterns are used to resolve problems associated with contamination of silicon dioxide, and for more than the efficient extraction of uranium, than the method that uses ion-exchange resins of other types having different ionic strength.
In the first embodiment, the present invention relates to:
the method including:
a) obtaining a sample containing uranium and silicon dioxide;
b) processing the sample containing uranium and silicon dioxide, with the obtaining of material containing uranium and silicon dioxide, the material contains
(i) the number of SiO2greater than or equal to 100 mg/l; and
(ii) dissolved uranium,
b) removing dissolved uranium from the material using at least one strongly basic anion-exchange resin macrostate patterns with receipt containing uranium product in combination with strongly basic anion-exchange resin macrostate structure; and
c) elution and extraction containing uranium product from the combination obtained in stage b).
When used in the present invention, the term "anion exchange resin" is defined as the cross-linked polyelectrolyte containing cationic groups. Suitable cation-exchange groups include, but are not limited to, tertiary and Quaternary ammonium groups, which are associated with mobile anions.
When used in the present invention, the anion exchange resin macrostate patterns represent an anion exchange resin, operasie hard pores, hereinafter referred to as "macropores". The distribution of macropores in the particles of anion exchange resin is stable in time. The diameters of the macropores are in the range from a few to several hundreds of angstroms. Strong base resin macrostate structure proposed in the present invention have diameters of the macropores equal to from 100 to 400 Å, preferably from 120 to 350 Å and more preferably from 150 to 300 Å. Macropores are connected to each other to form a grid extending from the surface to the center of the resin beads. Due to such a structure outside of the solution can freely and without changing the ionic strength to flow through the pores of strong-base resins macrostate patterns from the surface of the resin inside. Porosity strongly basic anion-exchange resins proposed in the present invention, is from 0.15 to 0.50 ml/ml, preferably from 0.2 to 0.4 ml/ml and more preferably from 0.25 to 0.35 ml/ml
When used in the present invention "strong" anion-exchange resin is defined as anion-exchange resin containing Quaternary ammonium functional groups. Suitable strong base resin macrostate structure proposed in the present invention include, but are not limited to, type 1" or "type 2", with uniform or Gaussian distribution of particle sizes. Por the measures strongly basic anion-exchange resins macrostate patterns, proposed in the present invention include, but are not limited to, functionalized styrene-divinylbenzene and acrylic copolymers, in which the functional group is kvaternikova ammonium group. The contents of the strong-base groups in the copolymer stradivariuses containing quaternion ammonium groups, often exceeds 99%. Samples of strong-base resins macrostate patterns used in the present invention, can be obtained from the company Rohm and Haas Company. Examples of these strong-base resins macrostate patterns include, but are not limited to, resin Amberlite™ IRA900 CL, resin Amberlite™ IRA910U CL and Ambersep™ 920U CL or Lewatit™ MR WS and Lewatit™ MonoPlus MP500, produced by Lanxess Corporation.
When used in the present invention, "high silicon dioxide content" refers to the environment in which the silicon dioxide content in the material containing uranium and silicon dioxide, greater than or equal to 100 mg SiO2/l (100 ppm million). The silicon dioxide content in the material containing uranium and silicon dioxide, proposed in the present invention, is preferably from 100 to 3000 mg SiO2/HP
Traditionally, samples of uranium can be extracted from mines in the form of ore or can be retrieved in the form of leachate; however, experts with General training in the art can relogit other conventional extraction technology samples the uranium and they can be used in the present invention. After receiving the sample using one or more of these methods, the sample should be turned into a containing uranium and silicon dioxide material proposed in the present invention. Then the sample can be subjected to leaching and get the material. The material proposed in the present invention, contains dissolved uranium and the amount of SiO2greater than or equal to 100 mg/l, but can contain other substances. The material, if it is obtained by leaching the sample can be called leachate. When used in the present invention "leachate" is defined as the product obtained after containing uranium and silicon dioxide material was subjected to the leaching procedure. The leachate may contain materials that are in one or more aggregate States, such as solid, liquid and colloidal materials. In one embodiment, the leachate is liquid. Although the present invention for receiving material from the sample described methods of leaching, it is possible to use other techniques known to experts in the field of technology, provided that the resulting material contains dissolved uranium and the amount of SiO2greater than or equal to 100 mg/L.
The leaching procedure can be what about any of the following technologies, including, but not limited to, in situ leaching, heap leaching and periodic leaching.
After leaching of the contained uranium and silicon dioxide and receipt of dissolved uranium dissolved uranium can be removed from material containing uranium and silicon dioxide, using at least one strongly basic anion-exchange resin macrostate patterns. Containing uranium product is formed in combination with strongly basic anion-exchange resin macrostate patterns. The combination is defined as containing uranium product included in the strongly basic anion-exchange resin macrostate patterns. In this case, the uranium is no longer dissolved. The right equipment for the extraction of uranium from liquid leachant includes, but is not limited to, ion-exchange columns with a fixed layer, ion-exchange columns continuous fluidized-bed, ion-exchange columns continuous moving bed, setting type resin-in-pulp and resin-in-leach solution".
After received containing uranium product in combination with strongly basic anion-exchange resin macrostate patterns, strongly basic anion-exchange resin macrostate structure must be separated from the containing uranium prospect the product and extract the resulting uranium. You can use the usual methods of separation containing uranium product and extraction of uranium. One way the Department containing the uranium product from the strongly basic anion-exchange resin macrostate structure is a strongly basic anion-exchange chromatography resin macrostate patterns. Chemicals suitable for elution containing uranium product from the strongly basic anion-exchange resin macrostate patterns, include, but are not limited to, a nitrate such as ammonium nitrate, a chloride such as sodium chloride, and sulfuric acid. These compounds can be used individually or in mixtures. In one embodiment, the equipment used for elution of uranium, is a system of continuous fixed bed comprising one or more columns.
Methods suitable for extract containing uranium product include, but are not limited to, ion exchange, liquid extraction, precipitation extract and their combination, for example liquid extraction and subsequent precipitation retrieval.
Received containing uranium product is a uranium extracted by applying a strongly basic anion-exchange resin macrostate patterns. Below the comparative example shows that this strong Ani is noumena resin macrostate structure resistant to contamination by silicon dioxide in environments with high silicon dioxide content.
Strongly basic anion-exchange resin macrostate patterns Amberlite™ IRA910U CL and gel-type strongly basic anion-exchange resin Amberjet™ 4400 CL was placed in drums and Rössing uranium mine, Namibia, through them within 8 months of missed the thread leach solutions containing 150-200 ppm million of uranium, 20 g SO4/l, 1 g Fe/l and 500-700 mg/l SiO2at pH 1.8. After this treatment the samples of resin were extracted, analyzed, and determined, and compared with the new results of their performance on uranium extraction.
In table. 1 shows the characteristics of the resin after use.
|Designation sample||Full capacity (EQ./l resin)||Humidity (%)||% SiO2|
|Jt440 comparative sample 1||1,6||43||0|
|Jt4400 comparative sample 2||1,6||42,2||1|
|Jt4400 comparative sample 3||1,5||41||8|
In table. 1 sample IRA910U denotes a resin Amberlite™ IRA910U CL and Jet4400 denotes a resin Amberjet™ 4400 CL. Samples I910U-sample 1 and Jt4400 comparative sample 1 denote the resin in new condition; all other samples are resins after use, containing a specified amount of silicon dioxide.
The samples were studied as follows: 100 ml of the resin was placed in a column and through the layer of resin at a flow rate of 5 OC/h (OS = volume of the layer), and when the ambient temperature is passed the experimental solution containing 75 mg uranium/l, 0.24 g Fe/l and 24 g SO4/l at pH 1.8. First, the samples were subjected to complete elution, so that in the resin uranium was not detected or was detected very small amounts of uranium. In the first cycle, the resin was extracted supplied solution and regenerates using OS 5 13% H2SO4at a flow rate of 1 OC/h and at ambient temperature, then was replaced by water with the aid of the rd 3 OS water. Then there was the second cycle, which was determined by the concentration of uranium in facing the flow (leakage) and the capacity of the resin was calculated for the endpoint corresponding to 90% of the applied concentration.
The results obtained in the second cycle are shown in table. 2.
|Designation sample||Initial leak of uranium (mg U3O8/l)||Capacity (g U3O8/l resin)|
|Jt4400 comparative sample 1||4||45,2|
|Jt4400 comparative sample 2||9||37,7|
|Jt4400 comparative sample 3||19||20,0|
As can be seen from the table. 2, resin Amberlite™ IRA910U CL in fresh condition led to less started the Noah leakage of uranium, than the resin Amberjet™ 4400 CL, but had a lower capacity. Samples 2 and 3 both resins after contamination by silicon dioxide led to a significant leak and a smaller working containers. The values of capacity reduction, expressed as a percentage of the capacity of the new resins are shown in table. 3.
|The decrease of working capacity compared with the new resin (%)|
|Amberlite™ IRA910U CL||Amberjet™ 4400 CL (comparative)|
Found that the relative reduction of the capacity for resin Amberlite™ IRA910U CL was significantly less than for resin Amberjet™ 4400 CL, despite the fact that in the resin Amberjet™ 4400 CL a silicon dioxide content was much lower.
The increase in leakage means that the portion of the uranium is extracted and discharged to the output stream (waste). This stream must be processed to extract the uranium, otherwise it will be lost. This operation reduces the performance of the installation. As can be seen from the of the GLA. 2, Amberjet™ 4400 CL, samples 2 and 3, resulted in 2-3 times greater leakage of uranium compared with the corresponding samples of the resin Amberlite™ IRA910U Cl.
Overall, therefore, the resin macrostate patterns Amberlite™ IRA910U CL contaminated with silicon dioxide, resulted in a relatively smaller decrease in capacitance and lower leakage of uranium than the resin of the gel type Amberjet™ 4400 CL contaminated with a smaller amount of silicon dioxide than resin Amberlite™ IRA910U CL.
1. The method of extraction of uranium from solutions with a high silicon dioxide content, including obtaining a sample containing uranium and silicon dioxide, the processing of a sample containing uranium and silicon dioxide, with the obtaining of material containing dissolved uranium and silicon dioxide, the material contains a number of SiO2greater than or equal to 100 mg/l, removal of dissolved uranium from the material using at least one strongly basic anion-exchange resin macrostate patterns with receipt containing uranium product in combination with strongly basic anion-exchange resin macrostate patterns and elution and extraction containing uranium product from the combination with strongly basic anion-exchange resin macrostate structure.
2. The method according to claim 1, in which the dissolved uranium is produced by leaching of the sample containing uranium and silicon dioxide, sulphuric acid.
3. JV the property according to claim 1, in which the composition of the strongly basic anion-exchange resin macrostate structure includes a styrene-divinylbenzene containing functional quaternion ammonium group.
4. The method according to claim 1, in which the strongly basic anion-exchange resin macrostate structure has a porosity comprising from 0.15 to 0.50 ml/ml
5. The method according to claim 1, in which the strongly basic anion-exchange resin macrostate structure has an average pore diameter of equal to from 100 to 400 Å.
6. The method according to claim 1, which contains the uranium product to elute at least one agent selected from the group including: ammonium nitrate, sodium chloride and sulphuric acid.
7. The method according to claim 1, which contains the uranium product is extracted by precipitation retrieval.
8. The method according to claim 1, which contains the uranium product is extracted by solvent extraction with subsequent precipitation retrieval.
9. The method according to claim 1, wherein the material containing dissolved uranium and silicon dioxide is liquid leachate sample, containing from 100 to 3000 mg SiO2/L.
SUBSTANCE: procedure consists in processing refractory ore and concentrates with chlorine at presence of water and complex former in kind of sodium chloride, in converting gold into solution, in separating solution from precipitated sediment, and in washing sediment with water producing flush water. There are processed refractory ore and concentrates with low contents of gold and uranium, where uranium is additionally extracted. Also, for processing there is used chlorine in atomic or molecular state. Chloride or sodium sulphate are used as complex formers. Processing is carried out at weight ratio L:S (liquid: solid) (1-1.5) during 1-2 hours at temperature 20-70°C with simultaneous gold and uranium passing into solution.
EFFECT: simplified process, reduced power expenditures at maintaining high degree of gold and uranium extraction from poor bases and concentrates.
7 cl, 6 tbl, 6 ex
SUBSTANCE: procedure consists in extracting uranium by means of liquid extraction of organic phase of synergy mixture on base of di(2-ethylhexyl)phosphorous acid containing tributylphosphate (TBP) or tributylphosphate together with trialkylamine (TAA) or heteroradical phosphynoxide of composition of oxide of isoamyldioktylphosphyne in organic thinner. Also, while mixing, there is performed simultaneous gradual neutralisation of mixture of phases with mineral acid till there are established balanced values of pH of water phase in interval 5.6-6.6.
EFFECT: increased efficiency of extraction of uranium and molybdenum from carbonate solutions.
3 dwg, 3 tbl, 3 ex
SUBSTANCE: procedure consists in sulphuric acid leaching of uranium. Also source material of 0.1-0.3 mm dimension is subjected to sulphuric acid leaching in autoclave till over 95% of uranium is transited to solution and till degree of pyrite oxidation reaches not less, than 50%. Upon separation of uranium containing solution from a solid phase in form of a cake the latter is conditioned by flotation of valuable metals with sulphydric collector and oxy-ethylated compound at pH 2.5-7.0 thus producing concentrate of valuable metals.
EFFECT: high degree of decomposition of persistent minerals of uranium and pyrite oxidation associating silver and gold and efficient extraction of uranium into water phase and valuable metals into floated concentrate.
17 cl, 1 dwg, 7 tbl, 5 ex
SUBSTANCE: invention refers to procedures for processing chemical concentrate of natural uranium. The procedure consists in dissolving natural uranium in solution of nitric acid, in directing solution to uranium extraction with tri-butyl-phosphate and hydrocarbon thinner, in washing extract with re-extract and in uranium re-extracting. There is dissolved chemical concentrate of natural uranium with increased content of phosphorus and sulphur. Uranium is extracted from solutions with increased concentration of phosphorus and sulphur and with concentration of nitric acid 30÷80 g/l to 60÷75% saturation of extractant with uranium. Also this level of extractant saturation with uranium in the said range in % is maintained not exceeding value equal to (0.3×[HNO3]+51), where [HNO3] is concentration of nitric acid in solution directed to extraction, in g/l.
EFFECT: purification of uranium at minimal uranium losses with raffinate.
SUBSTANCE: invention relates to atomic industry and can be applied in technological processes of obtaining uranium tetrafluoride and in production of metallic uranium. Method of obtaining uranium tetrafluoride includes dissolution of uranium dioxide, sedimentation of uranium tetrafluoride from obtained solution by supplying hydrofluoric acid. After that carried out are pulp filtration, sediment washing, drying and burning. Dissolution of uranium dioxide is carried out in mixed solution of hydrochloric and hydrofluoric acids obtaining solution of complex uranium compound with uranium concentration up to 480 g/l. Uranium tetrafluoride from solution is precipitated in form of crystal hydrate by dosed supply of hydrofluoric acid during 15-30 min, without forced heating of reaction medium.
EFFECT: increase of process productivity and reduction of expenditures.
SUBSTANCE: procedure consists in crushing and wet crumbling of source raw material producing pulp. Also ore containing brannerite is used as source raw material. Upon wet crumbling pulp is concentrated, leached with sulphuric acid and separated. Upon separation upper discharge is directed to counter flow sorption of uranium, while lower discharge containing brannerite fraction is acidated with sulphuric acid to 40-80 g/l producing acidic pulp with S:L<1:4. Produced acidic pulp is radiated with a flow of accelerated electrons at energy of absorbed radiation dose 1.5-1.6 kgr/s during 4-8 min. Further uranium is leached at mixing and at temperature 60-70°C during 2-3 hours and produced pulp is condensed. Upon condensation there is formed upper discharge which is supplied to source raw material leaching, while lower discharge goes to waste.
EFFECT: extraction of uranium from hard opened brannerite crude ore.
3 cl, 7 tbl, 1 dwg, 2 ex
SUBSTANCE: method includes graining of uranium ore, its sulphatisation by sulfur acid at presence of nitric acid. Additionally nitric acid is fed in amount required for oxidation of sulphides containing in uranium ore. Then received grains are subject to thermal treatment at temperature 200-300°C and leaching by water.
EFFECT: reduction of consumption of mineral acids for reprocessing of uranium ore and in increasing of uranium extraction.
SUBSTANCE: present invention relates to sorption hydrometallurgy of uranium. Described is a pyridine ionite based on a copolymer of styrene and divinylbenzene for sorbing uranium from solutions and pulp, distinguished by that the initial polymer matrix of the ionite additionally contains methacrylic acid in amount of 3.0-6.0 wt %.
EFFECT: obtaining an ionite with improved desorption characteristics; improved cost-performance ratio of the sorption-desorption process of extracting uranium from a solution.
2 cl, 3 tbl, 2 ex
SUBSTANCE: invention relates to hydrometallurgy, particularly to extraction of uranium and molybdenum from carbonate ores. Method includes crushing, grinding and high-volume sorptive leaching at presence of oxidants. Additionally after 2-4 stage of sorptive leaching of uranium and molybdenum into pulp there are introduced KMnO4 at its consumption 0.15-0.25% of ore mass and it is implemented after-oxidation of uranium and molybdenum during 40-60 minutes at absence of sorbent. After after-oxidation it is finished sorptive leaching.
EFFECT: reduction of oxidant consumption and total process duration.
2 tbl, 2 ex
SUBSTANCE: invention relates to technology of rare metals, particularly to method of processing of vanadium-bearing raw material: vanadium ores, vanadium-bearing slag of metallurgical manufacturing, treated vanadium catalysts and, particularly to complex treatment of Karatau quartzites by hydrometallurgy method. Method of processing of vanadium-bearing raw material includes acid leaching, sorption by resin of vanadium, uranium and phosphorus from solutions of leaching up to saturation of resin by vanadium, desorption of vanadium from resin and receiving of vanadium oxide. Additionally it is implemented double-circuit saturation of resin by vanadium: originally up to 200-250 g/kg by means of sorption from leaching solutions. Then it is complete saturate up to 450-650 g/kg by treatment b solutions of vanadic acid containing not less than 15 g/l of vanadium oxide, with simultaneous extraction of uranium and phosphorus into mother solution. Desorption of vanadium from resin saturated by vanadium up to 450-650 g/kg is implemented by method of solid-phase or liquid-phase desorption. In the capacity of vanadic acid there are used strippings of liquid-phase desorption or solutions prepared from vanadate of ammonium.
EFFECT: upgraded division grade of vanadium from uranium and phosphorus and upgraded efficiency of process.
2 cl, 2 ex
SUBSTANCE: procedure consists in acid extraction of compounds of rare earth elements from phospho-gypsum by mixing extract suspension, in separation of insoluble sedimentation of crystal gypsum from extraction solution and in extracting compounds of rare earth elements from extraction solution. Also, acid extraction is performed with solution of mixture of sulphuric and nitric acids at ratio from 3.2 to 1.2 and concentration from 1 to 3 wt % at ratio L:S (liquid : solid) from 4 to 5 during 8-12 min with simultaneous hydro-acoustic effect onto mixed extraction suspension. Rare earth elements are extracted from extraction solution by means of cation-exchanging sorption with infiltration of extraction solution through cation-exchanging filter.
EFFECT: increased degree of extraction of rare earth elements and 2 times reduced time for process at lower concentrations and volumes of acid reagents.
3 cl, 2 tbl, 4 ex
SUBSTANCE: procedure consists in underground leaching nickel with solution of sulphuric acid and in pumping product solution out. Further, acidity of product solution is reduced, and nickel is sorbed on ionite resin with its following desorption. Upon desorption raffinate of nickel sorption is made-up with sulphuric acid and directed to leaching as leaching solution. Also, excessive sulphuric acid is sorbed on separate ionite with following desorption for reduction of product solution acidity. Upon nickel sorption raffinate is made-up with sulphuric acid and with sulphuric acid after operation of its desorption.
EFFECT: simplification of process, increased ecological safety and reduced consumption of sulphuric acid.
1 dwg, 1 tbl
SUBSTANCE: invention relates to method of extracting stibium from sulphate solutions. Proposed method comprises sorption on anionite and desorption of stibium from anionite by desorption solution. Sorption is carried out using Lewatit K 5517 anionite, while desorption is made via feeding desorption solution through stationary anionite layer at the rate of 0.35-0.46 m/h at 45-50°C. Desorption solution represents disulphide alkaline solution with molar ratio S/NaOH=0.5 and/or alkaline solution of sodium sulphide with sodium concentration of at least 26 g/l.
EFFECT: stibium extraction and increased stibium concentration in solution intended for electrolysis.
3 dwg, 3 tbl
SUBSTANCE: invention relates to method of extracting stibium and arsenium from solution of gold-containing concentrate bioleach solutions. Proposed method comprises sorption of stibium and arsenium on anionite. Note here that sorption is performed on Lewatit K 5517 anionite, and stibium and arsenium are desorbed there from. Prior to desorption, anionite is subjected to sulphuric-acid washing out of iron deposit. Washing-out comprises rinsing by 1.2-1.3%-sulphuric acid with S:L ratio equal to 1:4 at 45-50°C, flow rate of rinsing solution in anionite of 1.0-1.3 m/h, and dissolution of iron (III). Then, remaining iron (III) is washed out by 3%-solution of sodium sulphite at pH=1.5 and S:L=2.
EFFECT: higher yield of stibium and arsenium due to selective wags-out of iron for further desorption of them.
3 dwg, 1 tbl
SUBSTANCE: invention relates to the method of processing sulphide gold-containing concentrates. Proposed method comprises bioleach of concentrate involving stibium dissolution and extraction from solution by sorption. Note here that stibium sorption from bioleach solution is carried out on anionite Lewatit K 5517 at 45-50°C, anionite flow rate making 50-100 g/l of solution for 8-10 hours. After sorption, desorption is carried out.
EFFECT: expanded process performances, increased extraction of stibium of gold-containing ores.
2 dwg, 1 tbl, 1 ex
SUBSTANCE: sorption method of rhenium (VII) from water solution involves contact of the solution and absorbent at pH<5. At that, activated bone coal pre-treated with water or acid is used as absorbent.
EFFECT: effective extraction of Re ions from water solution.
4 dwg, 3 ex
SUBSTANCE: method for extraction of rhenium (VII) from the solutions containing non-ferrous metals involves preparation of solution and sorption of rhenium (VII). Sorption is performed from sulphate solutions containing cations of non-ferrous metals of nickel, cobalt or copper. The process is performed at mixing with AM-2"б" anionite or with absorbent bone coal at pH value of solutions, which is less than pH value of hydrolytic deposition of cations of non-ferrous metals.
EFFECT: increasing efficiency of selective extraction of rhenium from solutions of non-ferrous metals.
4 dwg, 3 tbl, 3 ex
SUBSTANCE: method involves contact of solution and anionite as absorbent. Sorption is performed at mixing. As anionite there used is porous anionite of mixed basicity of AM-2"б" grade, which is pre-treated with water, acid or alkali, and containing exchange groups CH2-N(CH3)2, .
EFFECT: optimisation of conditions of quick and effective extraction of rhenium ions from water solutions.
4 dwg, 3 ex
SUBSTANCE: invention relates to gold extraction from acid solutions by using high-capacity high-selectivity sorbent based on thiocarbamoilchitosan (TCC) with boding degree of 0.4-0.9 that is pretreated by 0.01-0.1 M-solution of hydrochloric acid for 1-2 h and, then filtered. Gold sorption is performed from acid chloride solutions at pH=1.0-1.5 and with periodic mixing. Sorbent capacity, as related to gold ions (III), approximates to 3.7 mmole/g.
EFFECT: increased gold yield without increased iron yield.
2 tbl, 20 ex
SUBSTANCE: procedure for hydro-metallurgical treatment of rhenium containing molybdenite concentrate consists in rhenium and molybdenum autoclave leaching with solution of nitric acid and in producing solution containing nitric and sulphuric acids. Further, residue in form of molybdenum acid is filtered and washed; molybdenum acid is dissolved in ammonia water and molybdenum and rhenium are extracted. Upon autoclave leaching rhenium is extracted from solution by sorption in two stages. At each stage duration of phase contact is 22-24 hours. Summary concentration of sulphuric and nitric acids at the first stage is maintained at ≤120 g/l and pH value at the second stage is maintained at 2-4. Molybdenum is extracted from a merged solution produced from the solution after sorption extraction of rhenium and from ammonia solution of dissolved molybdenum acid. Molybdenum is extracted by sorption in two stages at duration of phase contact 22-24 hours and maintaining pH value=1.5-2.0 at the first stage and pH=2.5-4.0 at the second stage.
EFFECT: increased output of molybdenum and rhenium into finish products, their high quality, simplification of process and its raised efficiency.
SUBSTANCE: invention relates to sorption-mediated recovery of molybdenum from solutions containing heavy metal cations. Method of invention comprises providing solution to be treated, sorption of molybdenum(VI) on anionite at pH < 7. Sorption is conducted from solutions with anionites AM-2b and AMP at solution pH below pH of hydrolytic precipitation of heavy metal cations but higher than pH of formation of molybdenum cations (pH ~ 1).
EFFECT: increased process selectivity and reduced number of stages in preparation of pure molybdenum.
9 dwg, 3 tbl, 4 ex