Abstract: This invention relates to the processing of liquid radioactive waste containing radioactively labeled biological molecules. More specifically, this invention relates to the use of solid phase binders to remove radioactively labeled biological molecules from liquid radioactive waste solutions.

Abstract: Metals and organics are extracted from solution by co-precipitating them with a gel comprising aluminum hydroxide and a complexing agent such as EDTA. After the gel is processed to remove the metals and organics, it can be recycled for further use by dissolving it in a high-pH solution, leaving no secondary waste stream. A number of alternative complexing agents perform better than EDTA.

Abstract: A method of preferential removal of cesium cations from aqueous solutions containing other inorganic cations. Deltahaedral heteroborane anions are added to the solution to form a salt with the cesium cations which then precipitates from the solution. The remaining dissolved Cs-deltahaedral heteroborane anion salt is then quantitatively sorbed on active charcoal to remove it from the solution.

Abstract: A continuous fluidized-bed contactor containing sorbent particles is used to remove solutes from liquid solvents. As the sorbent particles, for example gel beads, sorb the solute, for example metal ion species, the sorbent particles tend to decrease in diameter. These smaller loaded sorbent particles rise to the top of the contactor, as larger sorbent particles remain at the bottom of the contactor as a result of normal hydraulic forces. The smaller loaded sorbent particles are then recovered, regenerated, and reintroduced into the contactor. Alternatively, the loaded sorbent particles may also slightly increase in diameter, or exhibit no change in diameter but an increase in density. As a result of normal hydraulic forces the larger loaded sorbent particles fall to the bottom of the contactor. The larger loaded sorbent particles are then recovered, regenerated, and reintroduced into the contactor.

Abstract: The invention relates to the dissolving of plutonium and/or other radioactive elements in an aqueous solution by microwave heating.According to the invention, solid or liquid products containing plutonium and/or other radioactive elements are introduced into a container (7) containing an acid solution, comprising hydrofluoric acid and nitric solution, followed by the microwave heating of the solution containing these products using a chamber or tank (5) placed in a tight enclosure (1), which is supplied with microwaves by means of a coaxial cable or a waveguide (11) connected to the generator (9) located outside the enclosure.The solid products can be plutonium dioxide PuO.sub.2 or organic or mineral radioactive waste materials such as gloves, cellulose products, ion exchange resins, etc. The liquid products can be contaminated organic solvents such as tributyl phosphate in dodecane.

Abstract: A process for separating monovalent ions from a sodium-bearing radioactive waste stream which comprises contacting the sodium-bearing radioactive waste stream against at least one ion exchange membrane having permselectivity for monovalent ions wherein the monovalent ions permeate or diffuse across the ion exchange membrane to form a permeate of a monovalent ion-enriched stream and wherein a retentate is formed from the sodium-bearing radioactive waste stream which is substantially depleted of monovalent ions.

Abstract: A method for demineralizing water or an aqueous solution, which comprises contacting the water or the aqueous solution to be treated to a strongly basic anion exchanger made of a crosslinked polymer having a constituting unit of the following formula (I): ##STR1## wherein A is a C.sub.1-2 linear alkylene group, B is a C.sub.4-8 linear alkylene group, each of R1, R2 and R3 which may be the same or different, is a C.sub.1-4 alkyl group or a C.sub.2-4 alkanol group, X is a counter ion coordinated on the ammonium group, and the benzene ring D may have an alkyl group or a halogen atom as a substituent.

Abstract: Fission noble metals contained in an insoluble residue and/or a high-level radioactive liquid waste generated in the step of reprocessing spent nuclear fuels are dissolved in nitric acid to prepare a palladium-containing nitric acid solution, which is then brought into liquid-liquid contact with an extracting solvent containing a dialkyl sulfide in which each alkyl group has 4 to 10 carbon atoms as an extractant to extract the palladium component into the extracting solvent. The palladium-containing extracting solvent is brought into liquid-liquid contact with an aqueous thio compound solution or aqueous ammonia solution to strip the palladium component into the aqueous solution. A borohydride compound in added to the palladium-containing aqueous solution to precipitate palladium from this solution by reduction, and metallic palladium is recovered by separating the precipitate from the aqueous solution.

Abstract: Silicon is employed as a reducing agent in an acid bath to adsorb noble metals present as contaminants in the acid. In the manufacture of silicon devices for electronic memory and other devices, polonium-210 is adsorbed by silicon getters to reduce soft error rate attributable to alpha particle emissions from the radioactive polonium. The noble metals in addition to polonium which can be plated onto silicon using the disclosed method are gold, silver, platinum, copper, palladium, mercury, selenium and bismuth.

Abstract: In a method of separating neptunium and plutonium, a nitric acid solution containing a mixture of neptunium and plutonium is oxidized by irradiation of ultraviolet light in the presence of a reducing agent. As a result, different valences of neptunium are adjusted all into the valence 5, which can remain in water, and in the meantime, valences of plutonium are adjusted into the valence 4 or 6, which can be extracted in the organic phase. It is therefore possible to separate neptunium and plutonium from each other without difficulty.

Abstract: The method of treating liquid waste in a media is accomplished by exposing the media to phosphinimines and sequestering .sup.99 Tc from the media by the phosphinimine (PN) functionalities. The system for treating the liquid waste in the media includes extraction of .sup.99 TcO.sub.4.sup.- from aqueous solutions into organic solvents or mixed organic/polar media, extraction of .sup.99 Tc from solutions on a solid matrix by using a container containing PN functionalities on solid matrices including an inlet and outlet for allowing flow of media through an immobilized phosphinimine ligand system contained within the container. Also, insoluble suspensions of phosphinimine functionalities on solid matrices in liquid solutions or present on supported liquid membranes (SLM) can be used to sequester .sup.99 Tc from those liquids.

Abstract: An adsorbent useful for the adsorption of radioactive nuclides which comprises fibrous active carbon having a specific surface area of 1,000 m.sup.2 /g or more and an equilibrium moisture regain of 10% or more at a relative humidity of 45%; and a process for the volume-reduction treatment of radioactive liquid waste which comprises subjecting radioactive liquid waste containing radioactive nuclides to an adsorption treatment using an adsorbent comprising fibrous active carbon having a specific surface area of 1,000 m.sup.2 /g or more, and subsequently subjecting the spent adsorbent to an incineration treatment at a temperature which is equal to or higher than the ignition point of the fibrous active carbon.

Abstract: A method of separating and recovering Pu and Np from a Pu- and Np-containing nitric acid solution. The method comprises the steps of subjecting a nitric acid solution containing Pu and Np to valence adjustment by adding a reducing agent consisting of hydroxylamine nitrate and hydrazlne to said nitric acid solution so as to reduce Pu and Np in said nitric acid solution to Pu (III) and Np (IV), respectively; adjusting a nitric acid concentration of said nitric acid solution after said valence adjustment to 6 to 8 M; bringing said nitric acid solution after said nitric acid concentration adjustment into contact with a strong basic anion exchange resin so as to cause Np to be selectively adsorbed by said resin and to separate and recover Pu as a plutonium nitrate solution; and eluting said adsorbed Np (IV) by using diluted nitric acid of 1 M or below so as to recover Np as a neptunium nitrate solution.

Abstract: A method of adsorbing and separating a heavy metal element by using a tannin adsorbent comprising:(a) adjusting the pH of a solution containing a plurality of heavy metal elements to a predetermined pH;(b) contacting the adsorbent with the solution in which the pH thereof is adjusted;(c) adjusting the pH of the solution contacted with the adsorbent to a pH different from the predetermined pH; and(d) contacting the solution in which the pH thereof is adjusted at the step (d) with the adsorbent prepared at the step (a).According to the inventive method, all of the heavy metal elements can be efficiently separated and adsorbed by using a tannin adsorbent from a solution containing a number of heavy metal elements. A method of regenerating a tannin adsorbent are also disclosed.

Abstract: An ion exchange resin for extracting metal ions from a liquid waste stream. An ion exchange resin is prepared by copolymerizing a vinylidene diphosphonic acid with styrene, acrylonitrile and divinylbenzene.

Abstract: A process for the decontamination of solid surfaces contaminated with radioactive or heavy metal species using a solution based on one or more non-persistent complexing agents, or for the chemical cleaning of steam generator sludge using such a solution, or for removing radioactive or heavy metal species from a solution using a combination of a one or more non-persistent complexing agents and a solid support, followed in each case by thermal or thermal-chemical treatment to decompose said non-persistent complexing agent. The preferred non-persistent complexing agents are hydroxamic acids, and the most preferred is acetohydroxamic acid.

Abstract: The isotopes of boron, .sup.10 B and .sup.11 B, are separated by means of a gas-liquid chemical exchange reaction involving the isotopic equilibrium between gaseous BF.sub.3 and a liquid BF.sub.3 . donor molecular addition complex formed between BF.sub.3 gas and a donor chosen from the group consisting of: nitromethane, acetone, methyl isobutyl ketone, or diisobutyl ketone.

Abstract: A method for the removal of pollutant ions from an aqueous solution in which they are contained, which method includes the steps of:i) contacting the solution to be treated with particles of a composite magnetic resin which includes magnetic particles embedded in an organic polymeric matrix which either contains, or has attached thereto sites which are selective for the pollutant ions in the presence of other ions it is not desired to remove;ii) separating by magnetic filtration the composite magnetic resin particles from the solution;iii) subjecting the separated composite magnetic resin particles to regeneration using an appropriate regenerant solution;iv) separating the regenerated composite magnetic resin particles from the regenerant solution; andv) recycling the separated composite magnetic resin particles to step (i) of the method.

Abstract: An agent for capturing metal ions, which consists essentially of a cyclic inulooligosaccharide having from 6 to 8 molecules of fructose bonded by .beta.-2,1 bonds to form a cyclic structure, wherein hydroxyl groups may all or partially be alkylated.

Abstract: Solutions such as for example drinking water, ground water and extracting solutions contaminated with heavy metals and radioactive species, singly or in combination, are treated by first treating the contaminated solution with silicate and ammonium hydroxide solution precipitants. Then the contaminated solution is separately treated with an acid which gels, polymerizes and/or precipitates the contaminant-containing silica matrix to form an easily dewaterable and separable solid. The solid contaminants are readily removed from the cleansed solution by filtration means. The process utilizes a novel combination of steps which maximizes contaminant removal, minimizes waste volume, and produces a treatable waste solid. The preferred precipitants are sodium silicate, and ammonium hydroxide. The preferred mineral acid is hydrochloric acid.

Abstract: In processes of this invention aqueous waste solutions containing a variety of mixed waste contaminants are treated to remove the contaminants by a sequential addition of chemicals and adsorption/ion exchange powdered materials to remove the contaminants including lead, cadmium, uranium, cesium-137, strontium-85/90, trichloroethylene and benzene, and impurities including iron and calcium. Staged conditioning of the waste solution produces a polydisperse system of size enlarged complexes of the contaminants in three distinct configurations: water-soluble metal complexes, insoluble metal precipitation complexes, and contaminant-bearing particles of ion exchange and adsorbent materials. The volume of the waste is reduced by separation of the polydisperse system by cross-flow microfiltration, followed by low-temperature evaporation and/or filter pressing. The water produced as filtrate is discharged if it meets a specified target water quality, or else the filtrate is recycled until the target is achieved.

Abstract: A process for removal of metal ions from soil and methods for effecting such removal are described. The process is based on the growth of crop and crop-related members of the plant family Brassicaceae in metal-containing soils. These particular plants will absorb metals into their roots making them not leachable from the soils or will absorb the metal into their roots and transfer them to the shoots which can be easily harvested.

Abstract: A metal ion detection and quantification system in which the displacement of a radioactive isotope from a material that binds both the metal ion of interest and the radioactive isotope. The material in question binds the radioactive isotope with less force than the isotope of interest. The extent of release of the radioactive isotope is used to determine the concentration of the metal ion of interest. In one embodiment of the invention, the material used to bind the metal ion and radioactive ion is a protein of the metallothionein class of proteins.

Abstract: A method for immobilizing waste chloride salts containing radionuclides such as cesium and strontium and hazardous materials such as barium. A sodalite intermediate is prepared by mixing appropriate amounts of silica, alumina and sodium hydroxide with respect to sodalite and heating the mixture to form the sodalite intermediate and water. Heating is continued to drive off the water to form a water-free intermediate. The water-free intermediate is mixed with either waste salt or waste salt which has been contacted with zeolite to concentrate the radionuclides and hazardous material. The waste salt-intermediate mixture is then compacted and heated under conditions of heat and pressure to form sodalite with the waste salt, radionuclides and hazardous material trapped within the sodalite cage structure. This provides a final product having excellent leach resistant capabilities.

Abstract: A process for decontaminating radioactive material comprises the step of contacting the material with a dissolving composition to dissolve the contaminants in the material, said composition comprising a dilute solution of about 0.05 molar ethylene diamine tetraacetic acid, about 0.1 molar carbonate, about 10 grams per liter hydrogen peroxide and an effective amount of sodium hydroxide to adjust the pH of the composition to a pH from about 9 to about 11. Also included are the steps of separating the dissolving composition containing the dissolved contaminants from the contacted material and recovering dissolved contaminants from the dissolving composition that has been separated from the material. A composition for dissolving radioactive contaminants in a material, comprising a dilute solution having a basic pH and effective amounts of a chelating agent and a carbonate sufficient to dissolve radioactive contaminants is also provided.

Abstract: Spent nuclear reactor coolant system decontamination solutions are first processed to remove the radioactive burden and to separate metallic impurities using cation exchange resins. The cation-processed waste solution is then flowed through an anion exchange resin held between anion-permeable membranes within an electrochemical cell. The application of electric current to the electrochemical cell causes hydroxide ions to replace captured anions held on the ion exchange resin, thereby regenerating the anion exchange resin for subsequent processing. The displaced anions migrate into the anode compartment where they can be oxidized to carbon dioxide for simple disposal.

Abstract: Plutonium, strontium, and cesium found in aqueous waste solutions resulting from nuclear fuel processing are removed by contacting the waste solutions with synthetic zeolite incorporating up to about 5 wt % titanium as sodium titanate in an ion exchange system. More than 99.9% of the plutonium, strontium, and cesium are removed from the waste solutions.

Abstract: A method for decontaminating radionuclides and other toxic metal-contaminateThe U.S. government has certain rights in this invention pursuant to Contract Number DE-AC02-76CH00016 between the U.S. Department of Energy and Associated Universities, Inc.

Abstract: A method for stabilizing in-situ soluble heavy metal contaminants in carbonate-containing land or submarine formations which comprises introducing into the carbonate-containing formation an aqueous solution of calcium chloride, wherein the solution contains a stabilizing amount of calcium ions. The contaminants and the carbonate form coprecipitates with the calcium ions which are insoluble in formation fluids, therefore substantially inhibiting the remobilization of the heavy metals with groundwater. The method is effective with heavy metals which exist in both anionic and cationic form in carbonate-containing land or submarine formations. The method may be used to treat land formations hundreds of feet below the surface, landfill deposits, or submarine formations to reduce soluble heavy metal contaminants to a few parts per million.

Abstract: An ion exchange material for the removal of radioisotope cations such as the cations of caesium and strontium from an aqueous environment containing the radioisotope cation comprises a modified clinoptilolite produced by treating a natural clinoptilolite with sodium hydroxide at a concentration of approximately 2M or with hydrochloric acid at a concentration of from 0.1 to 5M for a suitable treatment time and at a suitable treatment temperature. The modified clinoptilolite is especially effective in the removal of radioisotope cations from an aqueous environment.

Abstract: Process for the conditioning or recycling of used ion cartridges.The invention relates to a process for the treatment of ion cartridges or elements ensuring the treatment of contaminated waters of storage ponds or pools for nuclear reactor fuels. By cartridge transfer and suction means, said treatment consists of extracting the ion exchange resins contained in the cartridge.When the resin has been extracted, a conditioning process makes it possible to decontaminate and then condition, independently of the resinous substance, the metal structure constituting the cartridge.When the resin has been extracted, a recycling process makes it possible to clean the impurities from the metal structure and fill it again with new resin.The invention has applications in the nuclear field and in particular in the field of treatment and conditioning of nuclear waste.

Abstract: An apparatus for providing an inventory of an isotopically enriched acidic solution of an element that is capable of forming a water soluble weakly acidic solution at temperatures amenable to ion exchange and having a lower molecular weight isotope fraction and a higher molecular weight isotope fraction is disclosed. This apparatus includes at least two ion exchangers, each being temperature dependent with respect to their storage capacity of said lower and higher molecular weight isotopes, a hot tank containing a hot tank solution and a cold tank containing a cold tank solution both flow coupled to the ion exchangers. A first series of valves is selectively operable to direct the hot tank solution to one of the ion exchanger and to direct the cold tank solution to the other ion exchangers. A second series of valves is selectively operable to direct the flow from the ion exchangers to either the hot tank or the cold tank. An analyzer for sampling the solution is located upstream from the hot tank.

Abstract: According to the present invention, a fibrous material having a property to adsorb radioactive nuclides in the form of ion or molecule onto its surface is added to a cement type hydraulic solidifying material used for a solidifying material, a waste container, a structure in disposal site and a back-filling material used for production of a waste form of radioactive wastes, whereby improvement of long-term endurance of the waste form, the structure and the like and diminishment of leaching of radioactivity from the waste form and the like can be simultaneously attained.

Abstract: A method is provided for reducing the radioactive material content of fluids withdrawn from subterranean reservoirs. The method involves deposition of sorbent solids within the reservoir matrix surrounding a production well to act as an in-situ filter for dissolved radionuclides present in reservoir pore waters. For this purpose, the sorbent solid is either a) precipitated within the reservoir matrix by the reaction of two or more carrier solutions or b) directly introduced into the reservoir as a solid component of a solid-liquid slurry using high-pressure injection techniques. Thereafter, fluids produced by the well contain significantly lower concentrations of radionuclides (e.g., principally radium and uranium ions), as radionuclides are removed from the inflowing reservoir fluids by means of ion exchange, adsorption, chelation, chemisorption, or coprecipitation with the in-situ filter medium.

Abstract: A process and an apparatus are provided which separate the lower molecular weight isotope fraction from the higher molecular weight isotope fraction of an element which forms a water soluble acid at temperatures amenable to ion exchange. The separation is accomplished by shifting the equilibrium constants for absorption and desorption by temperature variations of the acidic solution. The process and apparatus are preferably employed to enrich a boric acid solution in its boron-10 isotope fraction by employing the use of ion exchange resins which are capable of thermally storing and releasing boron isotopes.

Abstract: There is disclosed an insoluble tannin preparation process, in which a tannin is first dissolved in an aldehyde aqueous solution. Then, ammonia is added to the solution to produce a precipitate, and the resulting precipitate is subjected to aging. The insoluble tannin thus prepared is employed to treat a waste liquid. Furthermore, there is disclosed an adsorption process in which a tannin is first dissolved in a solution containing a material to be adsorbed. Thereafter, an aldehyde is added to the solution to produce a precipitate having tannin as a principal constituent. The material to be adsorbed is adsorbed to this precipitate.

Abstract: The invention relates to a process for immobilizing, by an hydraulic binder, radioactive ion exchange resins or IER, which can contain borates in a quantity which can reach up to the equivalent of 1000 g H.sub.3 BO.sub.3 /kg of dry IER, wherein the IER are decanted and then placed in contact for a maximum of three hours with an eluant solution of 100 to 300 g/l in Ca(NO.sub.3).sub.2 in the proportion of 1 to 2 l/kg of decanted IER, an hydraulic binder of low hydration heat being added to the medium of pH.gtoreq.9 so that the ratio of the water of the eluant solution to the binder (by weight) is between 0.3 and 0.5 and that the incorporation rate:dry IER/final product (by weight) is between 3% and 10%.

Abstract: The concentrations of residual heavy metal contaminants in the particulate material in a slurry produced in a particulate material washing process are monitored on-line and can be used to control the washing process. In alternative embodiments of the invention, x-rays, thermal neutrons or laser beams are directed at the slurry as it flows through a flow cell to induce emission of secondary x-rays, gamma rays or light, respectively, characteristic of the heavy metal contaminants and constituents representative of the solids contents of the slurry. These characteristic energies are measured and used to determine the concentration in ppm of the residual heavy metal contaminants in the particulate material within the slurry.

Abstract: A simple, low temperature process for separating uranium isotopes and producing substantially pure uranium isotope fractions from a crude uranium isotope-containing aqueous feed stock is provided. A uranium isotope-containing solution is fed to an anion exchange resin in a continuously rotating annular chromatograph as a suitable eluant is also simultaneously fed to the rotating chromatograph. A Uranium 235, a Uranium 238 and an impurity fraction are recovered from the chromatograph. The substantially pure uranium 235 and uranium 238 fractions may be subjected to further processing, preferably precipitation with ammonium hydroxide to produce ammonium diuranate, and then calcining to form uranium oxide rich in the desired isotope.

Abstract: A simple, low cost continuous process for separating and purifying zirconium and hafnium which eliminates liquid waste and facilitates the management of RCRA and LLW wastes is provided. An aqueous zirconium and hafnium--containing feed solution is prepared and fed to a continuously rotating annular chromatograph containing a bed of acid exchange resin. An acid eluant, such as hydrochloric acid, nitric acid, phosphoric acid or the like, is fed through the acid exchange bed while chromatograph is rotating, which separates the feed into substantially pure zirconium and hafnium fractions and into RCRA and LLW waste fractions. The zirconium and hafnium are processed further into nuclear quality zirconium and hafnium metals. The acid eluant is recycled for reuse in the chromatograph, and the RCRA and LLW waste fractions are disposed of in solid form.

Abstract: There is disclosed a waste treatment process for alkaline waste liquid in which substances to be removed exist in ionic and colloidal states. In the process, powdered tannin is added to the waste liquid to produce solid substance of the tannin and to capture the substances to be removed on the solid substance. Then, the waste liquid is subjected to filtration to thereby separate the solid substance including the substances to be removed.

Abstract: The invention is a process for selectively extracting strontium and technetium values from aqueous nitric acid waste solutions containing these and other fission product values. The extractant is a macrocyclic polyether in a diluent which is insoluble in water, but which will itself dissolve a small amount of water. The process will extract strontium and technetium values from nitric acid solutions which are up to 6 molar in nitric acid.

Abstract: A process for preparing a crystalline layered hydrogenphosphate in a shortened period of time in high efficiency, which comprises reacting a tetravalent metal compound with phosphoric acid or its salt at an elevated temperature with introducing steam into the reaction system. Crystalline layered cerium(IV) bis(hydrogen-phosphate), particularly cerium(IV) bis(hydrogen-phosphate) dihydrate prepared by the above process, has an excellent ability of selectively adsorbing cesium ion, and is useful as a cesium ion adsorbent.

Abstract: Cations and anions contained as impurities in a spent organic solvent can be removed by an alkaline aqueous solution passing through inside of hydrophobic porous membrane such as hollow fibers for capturing anions and by an acidic aqueous solution passing through inside of hydrophobic porous membrane such as hollow fibers for capturing cations at the same time so as to regenerate the organic solvent. An apparatus suitable for removing cations and anions simultaneously from the spent organic solvent is also provided.

Abstract: Spent nuclear reactor coolant system decontamination solutions are processed to remove the radioactive burden and to separate metallic impurities using ion exchange resins within an electrochemical cell. The application of electric current to the electrochemical cell causes hydrogen ions to replace captured cations held on the ion exchange resin, thereby regenerating the resin for subsequent processing. The displaced cations migrate into the cathode compartment. The radioactive burden and metallic impurities are removed from the cathode compartment of the electrochemical cell. In a particularly preferred process, the cations are plated onto the cathode and disposed of as solids.

Abstract: Removing radioactive contaminants from liquid hazardous material such as oil, includes recirculating the material between a processing tank and a filter medium. The material is heated to increase viscosity during the circulation through the tank and filters. Chemicals including chelating agents are added to enhance the removal of the radioactive elements. Water is added to the processing tank or upstream, in a settling tank, to effect a water wash of the liquid hazardous material. A pre-filter stage upstream of the settling tank is followed by a mid-range filter stage in the recirculation loop with the main processing tank. A finishing filter stage is in the outlet from the main processing tank.

Abstract: According to the invention, the oil is passed through a pulverulent material, such as an earth or clay, in the presence of an acid. The pulverulent material can be placed beforehand on a filter or can be mixed with the oil before filtration. If necessary, the oil is recycled through the filter up to complete decontamination.Application to the radioactive decontamination of oils used in the nuclear industry.

Abstract: An improved method of disposing of radioactive or hazardous liquid hydrocarbon compositions comprises placing the liquid hydrocarbons in a container and adding an organic ammonium montmorillonite in ratios of between about 1:2 and 3:1, by volume, respectively. The organic ammonium montmorillonite has at least 10 carbon atoms. A polar organic compound having between 1 and about 10 carbon atoms is also preferably added with the montmorillonite. Where the liquid waste material includes 5% or more of water in addition to the liquid hydrocarbon a minus 200 mesh sodium montmorillonite is also preferably added.

Abstract: An improved method of disposing of radioactive or hazardous liquid aqueous waste compositions having a substantial amount of dissolved solids comprises mixing the liquid under a high mechanical shear with a clay selected from the group consisting of attapulgite, sepiolite, and mixtures thereof. Water soluble or miscible organic liquids as well as liquid hydrocarbon mixtures thereof may also be solidified by utilizing the aforesaid clays together with an organic ammonium montmorillonite having at least 10 carbon atoms, the amount of montmorillonite used being proportional to the amount of liquid hydrocarbon present.

Abstract: The invention is a method for the encapsulation of soluble radioactive waste chloride salts containing radionuclides such as strontium, cesium and hazardous wastes such as barium so that they may be permanently stored without future threat to the environment. The process consists of contacting the salts containing the radionuclides and hazardous wastes with certain zeolites which have been found to ion exchange with the radionuclides and to occlude the chloride salts so that the resulting product is leach resistant.