FIELD OF THE INVENTION

The present invention relates generally to the recovery of metal values, particularly to the recovery of tantalum, and to the recovery of metal values and acid values from certain residues which can contain naturally occurring radioactive elements such as uranium.

BACKGROUND OF THE INVENTION

There are numerous proposed schemes by which various natural ores, concentrates and slags may be processed for the recovery of metal values. Commercial schemes for the extraction and separation of tantalum and niobium (also known as columbium) values from beneficiated ores or from the widely available tin slags, are described in detail in U.S. Patent Nos. 2,767,047; 2,953,453; 2,962,372; 3,117,833; 3,300,297; 3,658,511; 3,712,939 and 4,164,417. In these prior processes, feed solids were generally digested with hot, concentrated hydrofluoric acid to solubilize most of the tantalum and niobium values as fluorides. A liquor containing the dissolved metal values is separated from the undissolved solids and is treated in a multistage liquid-liquid extraction cascade wherein the metal values are extracted with methylisobutyl ketone (MIBK). The residue from the primary process contains insoluble metals such as uranium and thorium, and also contains within the entrained insoluble matter quantities of dissolved tantalum and niobium. Stockpiling of these primary process residues results in the loss of revenues from the unrecovered metal values.

A general discussion of other ore process schemes is found in Extractive

Metallurgy of Niobium. Tantalum and Vanadium. INTERNATIONAL METALS

REVIEW, 1984, vol. 29, No. 26, BB 405-444, published by The Metals Society (London) and in The Encyclopedia of Chemical Technology. 3rd ed., Vol. 22 pp

547-550.

An improvement to a method in which hydrofluoric acid is used for the secondary recovery of tantaluift is disclosed in commonly assigned United States Patent No.

5,023.059, entitled, "Recovery of Metal Values and Hydrofluoric Acid from Tantalum and Columbium Waste Sludge" .

It is believed, therefore, that a process that would recover additional metal values from residues that contain such metal values as complexed fluorides: provide for the recovery of acids from the residues: and produce a solid waste residual that would be non-hazardous under all EPA listings and characteristic tests, and low enough in uranium and thorium content to be suitable for disposal as low-level radioactive waste, would constitute a desirable advancement in the art.

It is an object of this invention to provide an efficient process for the recovery of metal values from residues of the dissolution of ores and concentrates.

It is another object of this invention to provide an improved process for the recovery of metal values from dilute aqueous process streams.

It is a further object of this invention to recover portions of the sulfuric acid and hydrofluoric acid streams.

It is still another object of the present invention to provide a metal values recovery process, suitable for handling dilute source solids, that will generate solid and liquid waste products that are non-hazardous under EPA\'s toxic characteristic leaching procedure and all other EPA hazardous characteristics and listing, and that can therefore be disposed of legally either as low-level radioactive waste or as non-hazardous, non- radioactive waste, depending on residual uranium and thorium content.

It is yet a further object of the present invention to provide an efficient process for the recovery of metal values from residues of the dissolution and concentrates which results in reduced quantities of solid and liquid waste products.

Accordingly, the present invention comprises a process for recovering metal values from a source material containing at least tantalum or niobium and metallic

fluorides where the source material is digested with sulfuric acid to form a slurry. The slurry, upon separation, has both a solid and a first liquid aqueous phase. The liquid phase is contacted with a water immiscible organic liquid suitable for extracting tantalum values. A first organic phase bearing tantalum values and a second aqueous phase bearing uranium values is formed. The first organic phase is contacted with an aqueous liquid such as water to form a third aqueous phase containing the tantalum values. Tantalum values are then recovered from the third aqueous phase.

In an alternative embodiment, the separated solids from the digested source material are subjected to pyrohydro lysis. This process provides for the recovery of sulfuric and hydrofluoric acids from the solids and renders the leftover solid residuals non-hazardous under EPA listings and characteristic test, and therefore permissible for disposal as low level radioactive waste.

In another embodiment, the uranium bearing second liquid aqueous phase is brought into contact with an ion exchange resin to form a uranium depleted phase.

BRIEF DESCRIPTION OF THE DRAWINGS

Figure 1 is a schematic block diagram showing an integrated system for recovering metal values from secondary residues according to the process of the present invention.

Figure 2 is a schematic block diagram showing a solvent extraction process for the removal of uranium from one of the streams of the metal value recover}\' process.

DETAILED DESCRIPTION

For a better understanding of the present invention together with other and further objects, advantages and capabilities thereof, references made to the following detailed description and appended claims in connection with the above summary of the invention and the brief description of the drawings.

As best seen in Figure 1. the process of the present invention is performed in a system, which includes a digestion step 10. a separation step 12, an extraction and concentration step 16 and a metal recovery step 17. A pyrohydrolysis step 14 provides for the recovery of sulfuric and hydrofluoric acids while rendering the solids suitable for low level radioactive disposal. The digestion step reduces the quantity of gangue materials in the radioactive source. Either an ion exchange step 18 or alternatively, a solvent extraction process, illustrated in Figure 2. can be used to remove uranium which can be followed by a lime treatment step to provide a safe mariner for disposing of remaining liquids and solids.

The present invention provides an efficient process for the recovery of metal values, particularly tantalum from solids containing metallic fluorides, such as secondary residues resulting from the processing of ores and concentrates.

Typical secondary residues that can be processed by this invention are shown in

Table 1.

With particular reference to Figure 1. in the first step of the process, typically, sulfuric acid 20 is thoroughly mixed with a slurry of a secondary residue 22, typically, in a ratio of from about 0.3 to about 0.5 parts by weight of commercial concentrated sulfuric acid per 1 part by weight of solids in the slum\'. The slurry is maintained at about 70°C to about 100°C for at least about 5 minutes and preferably 30 minutes. While lower temperatures such as ambient can be used, the time period for digestion is increased. Higher temperatures result in increased fuming activity.

The slurry 24 is separated at 12 by known methods such as by filter press to form a first aqueous liquid phase 26 containing metal values such as tantalum and a solid phase.

When the residues shown in Table 1 were processed, the resulting liquid phase 26 typically contained from about 3 to about 8 grams of tantalum per liter. The first liquid aqueous phase 26 is contacted with a water immiscible liquid organic extractant suitable for extracting tantalum, such as MIBK, in extraction unit 16. A first organic liquid phase 28 containing tantalum values and a second liquid aqueous phase 32 are formed. Separation occurs by conventional methods of separating immiscible liquids. Tantalum and/or Niobium values are concentrated in a first organic extractant 28 to about 5 times the concentration present in the first aqueous phase 26. Phase volumes ratios are adjusted so that the extractant phase is one fifth less than the feed phase. Other methods known in the art may also be applied to increase concentration and to extract metal values. In order to completely remove at least the tantalum and niobium values, a free acid normality of greater than 4 is desired. A strong acid such as HCI or H ₂ SO ₄ is preferred. Complexed fluorides of tantalum and fluoride can be recovered by methods known in the art from the first organic liquid phase 28 such as by stripping with water 29. The solution containing the tantalum can be processed by conventional tantalum processing to produce tantalum of commercial purity. Niobium, if present, can also be recovered from the extractant by conventional techniques known to those skilled in the art.

The second liquid aqueous phase 32 resulting from the tantalum extraction unit 16 can be treated by an ion exchange resin in unit 18 to remove the uranium. The second liquid aqueous phase 32 generally will contain a concentration of uranium from about 0.05 to about 0.3 grams per liter. The ion exchange resin is stripped preferably with sulfuric acid 33. Other stripping agents known to those skilled in the art can be used. The stripping step yields an aqueous solution 34 having a concentration of about 10 grams per liter to about 30 grams per liter of uranium. This solution can be further processed to yield purified uranium. The uranium depleted phase 35 can be sent to a waste treatment plant 50 for lime 66, and filtration treatment at 58, and final disposal.

Alternatively, the second liquid aqueous phase 32 containing the above-mentioned concentration of uranium can be processed by solvent extraction in accordance with the process of Figure 2. A water immiscible organic extractant 60 typically comprising an organo-phosphate in a water-immiscible organic solvent is used to extract essentially all of the uramum. A preferred extractant is a mixture of di-2-ethylhexyl phosphoric (DEPA) and trioctyl phosphine oxide (TOPO). While various concentrations of the foregoing extractants can be used, it is preferred to use a mixture of 0.9 Molar DEPA and 0.13 Molar TOPO in a suitable organic solvent, such as kerosene. This organic extraction solution is used to contact second aqueous phase 32 in a mixer settler unit 61 to form an organic phase containing essentially all the uranium 62, and an aqueous phase containing only very low levels of uranium, 54. After settling, phases 54 and 62 are separated. The organic phase 62 is transferred to a stripping unit 64. A stripping agent such as an aqueous ammonium bicarbonate solution 65 is used to strip the uranium from the extractant solution to form an aqueous solution 66 containing a concentration of uranium of from about 2 to about 20 grams per liter which can be processed by techniques known to those skilled in the art for recovering uranium such as set forth in the Encyclopedia of Chemical Technology, supra, vol 23, pp 520-526. While ammonium bicarbonate is preferred, other stripping agents such as phosphoric acid containing sufficient ferrous iron ions to reduce the uranium to the U ⁺⁴ state can also be used. The uranium depleted aqueous phase 54 is treated with lime 66 and separated, for example, by filtration to yield an effluent stream 69 which contain essentially no uranium. The solid filter cake is suitable for disposal as hazardous, non-radioactive

industrial waste. Typical analyses of the solids 70 after lime treatment of the process illustrated in Figure 2 are shown in Table 2 below:

u= undetected on the basis of Toxic Characteristic Leaching Procedure, Method 1311, EPA 40CFR 261.

Regarding Figure 1, the solid phase 39, containing sulfate and fluoride ions is separated from the liquid phase and is subjected to pyrohydrolysis as follows: first, the solid phase is fed to a kiln 14 and is heated in the presence of water vapor from about ambient temperamre to an elevated temperature of at least about 700°C. While temperatures as low as 700°C can be used, it is preferred to use higher temperatures such as about 1200°C in order to reduce the product volume. Water vapor is preferably provided by the combustion gases that result from providing heat to the pyrohydrolysis step 14. Alternatively, the water vapor can be supplied. Gaseous sulfuric acid 40 and hydrofluoric acid 42 are formed. Gaseous sulfuric acid 40 is condensed by a first scrubber 44 utilizing dilute sulfuric acid 46 and gaseous hydrofluoric acid 42 is condensed in a second scrubber 48 utilizing dilute hydrofluoric acid 55. The solids generated 52 from the process of this invention are chemically inert. The term "chemically inert" is defined herein as non-hazardous under EPA listings and characteristic tests and are suitable for disposal as low level radioactive waste. An average reduction in low level radioactive solids 52 of about 30 to 50 percent from the

dry weight per quart of residual solids 22 is obtained by the present invention. The recovered sulfuric acid 20 can be recycled to treat the incoming sludge if desired. Additionally, if metal values other than tantalum are present in the metallic fluoride containing residues, the metals can be solubilized using sulfuric acid. An aqueous solution is separated from the solids and the first liquid phase 26 is treated to remove the particular metal desired by means known in the an such as ion exchange or solvent extraction. In such instances, the solids are further processed to provide acid recovery as described above.

To more fully explain the preferred embodiments of the invention the following non-limiting detailed example is presented. All parts, proportions and percentages are by weight unless otherwise indicated.

EXAMPLE

Using the process as illustrated by Figure 1 about 65000 parts of a secondary residue containing 40% water are digested with about 13650 parts of concentrated sulfuric acid and 26,000 parts of water for about 30 minutes at about 75°C. Thereafter, the resulting two phase mixture is separated using a high pressure plate and frame filter press.

The high pressure filter press operation results in a filter cake of solids containing about 35% moisture. The cake is placed onto a conveyor belt which feeds a sintering kiln. The cake, after going through a breaker is screw-fed to the kiln which is about 3 feet in diameter and about 25 feet long and is lined with a high temperature alumina refractory. The cake 2is heated to about 1200°C resulting in the evolution of a major portion of the HF and H ₂ SO ₄ as gases. These gases upon exiting the kiln are sprayed with water in a chamber to remove entrained solids, after which, the gases are scrubbed in two scrubbers which first recover the sulfuric acid by scrubbing with a dilute solution of sulfuric acid and secondly recovering the HF as a 40 % solution by scrubbing with an initially dilute solution of HF until the concentration increases to the 40% level. The gases, depleted of the majority of the acids, are then sent to a final scrubber to be

scrubbed with a sodium hydroxide solution to remove essentially all of the remaining HF before discharging the gas to the atmosphere. About 1 ,170 pans of HF are recovered from the 39000 pans of secondary residue. About 25000 parts of solids are discharged from the kiln.

The filtrate from the filter press has a concentration of metal values tantalum oxide and niobium oxide of from about 3 to about 8 grams per liter each. It also contains uranium oxide at a concentration of from about 0.02 to about 0.06 grams per liter. Tantalum and niobium are extracted from the filtrate using MIBK as an extractant. About 680 pans of tantalum oxide and 710 pans of niobium oxide are recovered by stripping from the extractant with water.

About 25 pans of uranium can be removed from the tantalum depleted material by either ion exchange or by solvent extraction.

When ion exchange is used, the tantalum depleted phase is brought into contact with an ion exchange resin to remove the uranium and the uranium values are stripped from the ion exchange resin by sulfuric acid.

When solvent extraction is used, the tantalum depleted phase is brought into contact with an organic extractant that is selective for uranium as is known in the an. A preferred extractant is a mixture of 0.9 M DEPA and 0.13 M TOPO in kerosene as was previously described. Ammonium bicarbonate solution is used to strip the uranium values from the extractant. A concentration of about .5 moles per liter of ammonium bicarbonates is introduced to the organic extractant. An ammonium bicarbonate solution having a concentration of about 2 to about 20 grams per liter of uranium is obtained which can be further processed by conventional uranium recovery methods. The pH is adjusted by conventional means to between about 8.4 to 8.65. For a flow of extract (organic phase) of 3 gpm. the stripped extractant flow rate would be about .04 gpm. The stripped organic extractant is recycled into the mixer settler. The streams from which the uranium has been removed are treated with an aqueous solution of lime having a concentration of about 200 grams of lime per liter and filtered. The effluent stream.

with essentially no uranium may, be discharged as non-hazardous, non-radioactive industrial waste. The solid filter cake is composed of calcium fluoride and calcium sulfate and is chemically inert.

While there has been shown and described what are considered to be the preferred embodiment of this invention, various changes may become apparent to those skilled in the art. These embodiments are not presented as limiting the invention but are set forth as an explanation of the invention which is defined by the appended claims.