Abstract: A process for the selective concentration of uranium from sea water through chemical accumulation onto a solid adsorption medium, which does not necessitate any H.sup.+ ions for regeneration, in particular onto titanium oxide hydrate and subsequent elution with a carbonate-containing eluent.

Abstract: A novel polyether having the following general formula: ##STR1## wherein R.sub.1, R.sub.2 and R.sub.3 each stand for hydrogen or an alkyl group. The polyether can capture cations, especially alkali metal ions, when contacted with a cation-containing aqueous alkaline liquid and can release the cations to an aqueous acidic liquid, and thus serves as a cation carrier.

Abstract: Use of activated carbon having a net pore volume of at least 0.40 cc./gram for those pores having a pore diameter of from 35 to about 1000 .ANG. to remove dissolved organic components from a uranium leachate solution.

Abstract: A method for oxidation of reduced cations and humate constituents of filtered, wet process phosphoric acid comprising the step of treating the acid with an oxygen source in the presence of activated carbon.

Abstract: A generator of radionuclides such as technetium-99m comprises a generator column (10) containing the radionuclide, a first reservoir (16) for eluent, a second reservoir (18) to contain a volume of the eluent required for a single elution, and a vessel 40 to contain eluate. First, a pre-set volume of eluent is transferred from the first to the second reservoir; then the eluent is sucked from the second reservoir through the column into the eluate vessel. A hydrophobic filter 32 adjacent the second reservoir (18) permits the use of air to dry the column (10) and to bring the partly filled eluate vessel (40) to atmospheric pressure.

Abstract: Aqueous ammonium uranyl tricarbonate strip solution is purified by using activated carbon to remove ammonium di(2-ethylhexyl)phosphate impurity.

Abstract: What is disclosed are novel metal chelating agents which are bonded to inorganic substrates to immobilize them. An example of such a metal chelating agent is (CH.sub.3 O).sub.3 Si(CH.sub.2).sub.3 NH(CH.sub.2 CH.sub.2 NH).sub.2 (CH.sub.2).sub.3 Si(OCH.sub.3). An example of an inorganic substrate is a silica gel.

Abstract: Zeolite is contacted with an aqueous solution containing at least one of copper, nickel, cobalt, manganese and zinc salts, preferably copper and nickel salts, particularly preferably copper salt, in such a form as sulfate, nitrate, or chloride, thereby adsorbing the metal on the zeolite in its pores by ion exchange, then the zeolite is treated with a water-soluble ferrocyanide compound, for example, potassium ferrocyanide, thereby forming metal ferrocyanide on the zeolite in its pores. Then, the zeolite is subjected to ageing treatment, thereby producing a zeolite adsorbent impregnated with metal ferrocyanide in the pores of zeolite. The adsorbent can selectively recover cesium with a high percent cesium removal from a radioactive liquid waste containing at least radioactive cesium, for example, a radioactive liquid waste containing cesium and such coexisting ions as sodium, magnesium, calcium and carbonate ions at the same time at a high concentration.

Abstract: Method of and apparatus for concentration of trace material from large voes of water. Carrier bodies having a lower density than that of water are introduced into a water layer, especially a natural sea current or stream; these carrier bodies are collected again after an automatic traversal of the sea flow or water layer under conditions determined by density differing from that of water. The carrier bodies are loaded and charged by depositing or accumulation of trace material, e.g. uranium concentration, on the carrier bodies. The carrier bodies are then conveyed to a further treatment location for isolating the accumulated and concentrated trace material. The carrier bodies are then again discharged into the flow or stream after being depleted.

Abstract: Dissolving hard-to-dissolve nuclear fuels such as ThO.sub.2 and PuO.sub.2 in a nitric acid fission material solution which contains nitric acid and a Pu-fluoride complex to provide free fluorine ions in a small catalytically active amount due to small dissociation of fluoride ions from the Pu-fluoride complex. This permits dissolving hard-to-dissolve nuclear fuels in normal metallic dissolving vessels and also eliminates need for using polytetrafluoroethylene.

Abstract: A novel polyether having the following general formula: ##STR1## wherein R.sub.1, R.sub.2 and R.sub.3 each stand for hydrogen, an alkyl group having 1 to 20 carbon atoms or an alkenyl group having 1 to 20 carbon atoms with the exception that R.sub.1, R.sub.2 and R.sub.3 cannot stand for hydrogen at the same time, and m and n each represent an integer of 1 to 9. The polyether can capture cations when contacted with a cation-containing aqueous alkaline liquid and can release the cations to an aqueous acidic liquid, and thus serves as a cation carrier.

Abstract: The invention is a process for the removal of radium from acidic aqueous solutions. In one aspect, the invention is a process for removing radium from an inorganic-acid solution. The process comprises contacting the solution with coal fly ash to effect adsorption of the radium on the ash. The radium-containing ash then is separated from the solution. The process is simple, comparatively inexpensive, and efficient. High radium-distribution coefficients are obtained even at room temperature. Coal fly ash is an inexpensive, acid-resistant, high-surface-area material which is available in large quantities throughout the United States. The invention is applicable, for example, to the recovery of .sup.226 Ra from nitric acid solutions which have been used to leach radium from uranium-mill tailings.

Abstract: The present invention relates to an improved method for the recovery of uranium values from a uranium-containing lixiviant by passing the lixiviant through a heated ion exchange resin to cause the resin to retain uranium values. The uranium values are subsequently recovered from the ion-exchange resin.

Abstract: A method and apparatus for recovering raw material, especially uranium, f natural waters, especially from the sea. Carrier bodies capable of sinking are permitted to pass, in a free fall, through a layer of water, especially a natural sea current or stream, by concentration on the carrier bodies, which are collected at an appropriate depth and are then conveyed from there for further treatment. Carrier bodies of inert material are used having a protected outer surface with a thin layer, capable of being concentrated, coated thereon. The distance of falling amounts to approximately 100 meters. The apparatus for carrying out the method includes a carrier body discharge located below water level. One end of a carrier body path has a collection device for collecting carrier bodies and is directed toward the conveyor path. The apparatus also has a conveying device operating especially hydraulically according to the principle of communicating pipes.

Abstract: A modified liquid-liquid extraction system is disclosed in which a particulate solid and a liquid, both insoluble in a second liquid, are mixed to form agglomerate particles which efficiently extract metal ions from dilute solutions. The extraction is rapid and requires a much lower volume of extracting phase for good contacting than conventional liquid-liquid extraction. Mixing energy is low, clean-up of effluent water is easily accomplished and metal values are readily stripped from the agglomerates by well-known techniques, such as treatment by aqueous acid solution.

Abstract: A nuclear fuel processing solution containing (1) hydrocarbon diluent, (2) tri-n-butyl phosphate or tri-2-ethylhexyl phosphate, and (3) monobutyl phosphate, dibutyl phosphate, mono-2-ethylhexyl phosphate, di-2-ethylhexyl phosphate, or a complex formed by plutonium, uranium, or a fission product thereof with monobutyl phosphate, dibutyl phosphate, mono-2-ethylhexyl phosphate, or di-2-ethylhexyl phosphate is contacted with silica gel having alkali ions absorbed thereon to remove any one of the degradation products named in section (3) above from said solution.

Abstract: A functionalized silica is prepared by reacting silica with a silane and an aromatic hydroxy aldehyde. The product is useful for removing metals from solution, e.g., Cu from ATK, or in the extraction of U from solutions arising from the processing of its ores.

Abstract: A process for the enrichment of one isotope in a mixture of uranium isotopes by passing a solution of the mixture in a solvent through an anion exchanger thereby forming on the anion exchanger a boundary (A) between a uranium adsorption zone and an adjacent reducing agent zone and/or a boundary (B) between a uranium adsorption zone and an adjacent oxidizing agent zone, the uranium adsorption zone advancing through the anion exchanger, effecting reduction at the boundary (A) and/or effecting oxidation at the boundary (B), thereby effecting enrichment adjacent said boundary, and separating a fraction enriched in one of said isotopes, which process comprises using as the solvent medium a composition comprising (a) a solvent having a dielectric constant of at least 80 at 20.degree. C., (b) hydrochloric acid and (c) at least one of hydrobromic acid and sulfuric acid, the solvent medium having a hydrogen ion concentration of about 0.1 M/l to about 10 M/l, a total chlorine ion concentration of about 0.

Abstract: This invention is a method for effecting preferential removal and immobilization of certain gaseous contaminants from gaseous UF.sub.6. The contaminants include fluorine and fluorides which are more reactive with CaCO.sub.3 than is UF.sub.6. The method comprises contacting the contaminant-carrying UF.sub.6 with particulate CaCO.sub.3 at a temperature effecting reaction of the contaminant and the CaCO.sub.3.

Abstract: A process is described for extracting phosphoric acid and metal values, such as uranium, from phosphate rock using hydrochloric acid and independently extracting the phosphoric acid and metal values from a slurry of the acidulated rock.

Abstract: Uranium or thorium cations are removed from aqueous suspension or solution by treatment of the aqueous material with the biomass derived from fermentation of a fungal microorganism of the genus Rhizopus, e.g. Rhizopus arrhizus. The process can be utilized to treat aqueous tailings from uranium ore extraction processes, to reduce the radioactive content of the tailings prior to disposal.

Abstract: The invention describes the extraction of values, especially metal values such as copper and uranium, from minerals by passing the mineral in admixture with a leaching agent for the values through a contactor and extracting the values with an extractant stream immiscible with the mixture and of lesser density so that the values are captured by the extractant and can be withdrawn with the extractant and, if desired, isolated by any suitable means.

Abstract: Granulated lignite (brown coal) is used to provide an adsorption matrix with which sea water is brought into contact long enough to reach a substantially maximum adsorption of uranium, after which the adsorption matrix is removed from the solution and is burned with utilization of its heating value while the heavy metals are concentrated in the combustion residue, after which the thus concentrated heavy metals are recovered in the form of their salts by previously known treatment. An average grain diameter of the granular lignite between 0.5 and 2 mm is used and about 3 mg of uranium per kg of dry lignite is adsorbed with a contact time in the region between one and sixty seconds. Uranium adsorption falls off when there is a substantially greater concentration of foreign ions, particularly calcium, magnesium and sulphate.

Abstract: Water is passed from a relative flow thereof in a horizontal direction, into a substantially vertical passage and through a bed of absorption material in a fluidized state, in order to extract a substance from the water. The static pressure of the water is increased by passing the water through a diffuser means before it passes into the vertical passage.

Abstract: A method and system for continuously extracting metals from sea water by deploying adsorber sheets in a suitable current of sea water, recovering the adsorber sheets after they become loaded with metal and eluting the metal from the recovered sheets. The system involves the use of hollow, perforated bobbins on which the sheets are rolled as they are recovered and through which elutant is introduced.

Abstract: A process as described for extracting at least two desired constituents from a mineral using a liquid reagent which produces the constituents, or compounds thereof, in separable form and independently extracting those constituents, or compounds thereof. The process if especially valuable for the extraction of phosphoric acid and metal values, such as uranium from phosphate rock.

Abstract: A method of quantitatively separating uranium from specimens of natural water, especially sea water or from solutions which as to their composition are comparable to such specimens, while silica gel is provided for adsorbing the uranium. The liquid of the specimens or solution is conveyed over granular silica gel having an average grain diameter not exceeding 0.5 mm. The through-flow speed is so selected that the contact time period for the liquid with the silica gel amounts to at least 50 seconds, whereupon the uranium adsorbed on the silica gel is separated therefrom by elutriation with at least 0.1 normal oxidizing mineral acid. The volume of the elutriate utilized, should amount to at least twice the volume of the silica gel, and this proportion of the elutriate should, if possible, not be exceeded.

Abstract: An isotope separation apparatus comprises a plurality of independent developing units, each comprising 2 to 20 adsorbent-packed columns forming a continuous developing circuit or passageway, and the developing units are connected to at least one common main pipe for supplying an isotope mixture solution, a regenerating agent solution, or an eluent solution. Also, in a further embodiment the developing units are connected to common liquid-discharge main pipes.The separation or concentration of isotopes such as uranium isotopes, nitrogen isotopes, boron isotopes, etc., is performed by continuously developing the isotope mixture solution passed through the individual adsorbent-packed columns successively in each developing units.

Abstract: This invention relates to removal of cerium, used as a free-radical initiator, from aqueous polymeric dispersions, particularly starch graft copolymer dispersions, by adsorbing cerium (III) onto a strong cation exchange resin, to separation of the adsorbed cerium (III) from the resin using a solution such as sodium sulfate or sodium oxalate to form a cerium (III) precipitate, and to oxidation of the separated cerium (III) to cerium (IV).

Abstract: A method for recovering uranium ions from sea water utilizing an adsorbent atrix. The materials contained in the matrix comprise biologically recent humic acids. Matter which serves as carrier material for the humic acids is present in the dry state up to 99% by weight.

Abstract: Molybdenum is recovered from an ammonium molybdate solution containing phosphate anions by digesting in an ammonium molybdate solution at least one water-soluble compound of at least one metal selected from the group consisting of aluminum, calcium, iron and magnesium in small but effective amounts to precipitate at least about 50% of the phosphate anions for a time sufficient to precipitate the phosphate anion, separating the phosphate precipitate from the ammonium molybdate solution, then acidifying the ammonium molybdate solution with at least one mineral acid selected from the group consisting of sulfuric acid and nitric acid to lower the pH value of the solution to between about 2.5 and about 4.5 to precipitate ammonium polymolybdate, and calcining the ammonium polymolybdate at a temperature below about 750.degree. C. to produce a molybdenum trioxide product.

Abstract: A novel titanium dioxide hydrate is provided whose structure exhibits X-ray diffraction peaks at 24.6.+-.0.4.degree. and 48.+-.0.4.degree., and which is suitable as an adsorbent material. A process for preparing the novel titanium dioxide hydrate also is provided which includes hydrolyzing a specific titanium sulfate solution and thereafter flocculating colloidal titanium dioxide hydrate by the addition of a monobasic acid and recovering the titanium dioxide hydrate.

Abstract: Macroporous styrene polymer particles which have been partially pyrolyzed at temperatures between 300.degree. and 800.degree. C. to form non-functionalized, carbonaceous adsorbents, are functionalized according to this invention to produce weak base, strong base, weak acid or strong acid, dense ion exchange particles, or precursors thereof, using such reactions as halogenation, sulfonation, chloromethylation, chlorosulfonation and oxidation, alone or followed by aminolysis or other conventional functionalization reactions.

Abstract: A process for chemical enrichment of uranium with respect to a lighter one of its isotopes. The process consists in contacting uranium of valence state III and uranium of valence state IV, or a compound of uranium of valence state III and a different compound of uranium of valence state III. One of the phases which are contacted or the only phase is liquid. The system should be substantially free of elements which would cause uranium III to oxidize to valence IV.

Abstract: A process for the removal of heavy metals uranium and transition metals other than noble transition metals from solution by contacting the solution with the product obtained by reacting an inorganic solid eg. silica gel containing surface hydroxyl groups with a silicon compound of defined formula containing a free thiol group or a free amino group and either an --OR group or a halogen atom under conditions which effect reaction between the hydroxyl group and the --OR group or halogen atom thereby bonding the silicon compound to the inorganic solid.

Abstract: A process for continuously separating uranium isotopes by oxidation-reduction reaction using an anion exchanger comprising the steps of subjecting an eluant containing a deactivated oxidizing agent and a deactivated reducing agent as a mixture to oxidation to regenerate the deactivated oxidizing agent, separating the regenerated oxidizing agent from the eluant with an anion exchanger and reusing the regenerated oxidizing agent for continuing the separation of uranium isotopes.

Abstract: Molybdenum is separated from molybdenum-containing activated charcoal or char also containing small amounts of uranium obtained as a by-product in uranium leaching processes by stripping with an alkaline solution to provide a molybdenum-containing solution containing substantially less than 500 ppm U.sub.3 O.sub.8.

Abstract: Uranium is recovered from its solution through contact with a uranium-recovering material of higher resistance to water and higher mechanical strength comprising a weakly basic anion exchange resin having pyridine nuclei at its main chain or side chain, and a crossed-linked polymer structure with a high uranium selectivity at a high uranium-adsorbing speed.

Abstract: 12-alkyl-1,4,7,10-tetraazacyclotridecane of the formula ##STR1## wherein R is an alkyl group containing at least 8 carbon atoms. This compound can be used for capturing metal ions.

Abstract: High salt content, alkaline waste solutions containing plutonium and americium are contacted with a sodium titanate compound to effect removal of the plutonium and americium from the alkaline waste solution onto the sodium titanate and provide an effluent having a radiation level of less than 10 nCi per gram alpha emitters.

Abstract: Waste waters, particularly waste waters with radioactive contamination, are cleaned by a sorption-precipitating process, where the sorbent retaining cations are regenerated that is, activated, by a solution, the cationic component of which forms with anionic contaminations a precipitate, taking along cationic contaminations, and simultaneously sticking on the surface and within pores of the sorbent.

Abstract: The invention relates to a process for decontaminating or removing radionuclides from aqueous solution.

Abstract: An anion exchange resin particle provided with specific structure as well as specific functional groups is found to be suitable for uranium technology, especially for separation of uranium isotopes.

Abstract: A process for separation of uranium isotopes by chromatography through an anion exchange material is found to be improved in efficiency of separation as well as in productivity by addition of a catalyst for accelerating electron exchange reactions occurring in the system under conditions to retain uranyl ions on the anion exchange material preferentially over uranous ions.

Abstract: Uranium-235 is efficiently concentrated using a solution containing uranium-238 and uranium-235 by passing a solution containing uranium (VI) complex anions through a body of an anion exchange material to adsorb uranium (VI) complex anions on a portion of the anion exchange material and then passing a solution of a reducing agent through the anion exchange material thus retaining uranium in the form of the uranium (VI) complex anions to elute the uranium ions while reducing the uranium (VI) complex anions to uranium (IV) complex ions.

Abstract: Boron or uranium isotopes can be chemically separated and enriched with high speed and with high separating efficiency by using weakly basic anion exchange fibers having a diameter of not more than 100 .mu., an aspect ratio of at least 5 and an exchange capacity of at least 2 meq/g-dry fiber, which are packed in a column at a specific volume of 2.0 - 20.0 ml/g-dry fiber.

Abstract: A matrix of algae mutants and method of obtaining thereby uranium from sea water, according to which a matrix is prepared of uranium compatible algae mutants suitable for picking up uranium dissolved in sea water, which matrix is then placed in an area of the sea in which low and high tides pass streams of sea water through the above mentioned matrix.

Abstract: An improved process for continuous counter-current contact between a fluid to be treated and solid particles wherein the fluid flows through a column containing a plurality of contacting chambers each of which contains solid particles and in which intermittent transfer of the particles in a direction opposite to that of the fluid from each chamber to the chamber immediately adjacent is effected while maintaining a continuous flow of the fluid through the column.

Abstract: A process for chemical enrichment of uranium with respect to a lighter one of its isotopes. The process consists in contacting uranium of valence state III and uranium of valence state IV, or a compound of uranium of valence state III and a different compound of uranium of valence state III. One of the phases which are contacted or the only phase is liquid. The system should be substantially free of elements which would cause uranium III to oxidize to valence IV.

Abstract: A method of regenerating fuel and/or breeder elements with thorium as brer material for nuclear reactors. The fuel and/or breeder material is dissolved in an acid such as nitric acid, sulfuric acid or the like and the thus obtained solution is subjected to a liquid-liquid reaction with an extraction substance such as tributyl phosphate dissolved in an organic solvent. The fuel material and breeder material are enriched in the organic phase and the fission products remain in the aqueous phase, whereafter the fuel material and/or breeder material are converted into oxides, carbides etc. Prior to the above mentioned liquid-liquid extraction, the acid solution containing the fuel material and/or breeder material is passed over a sorption column in such a way that the number of mols of adsorbed .sup.233 Pa per time unit equals the number of mols of .sup.233 Pa disintegrating per time unit in the sorption column to form .sup.233 U.