Abstract: A solid ion-exchange material useful for removing heavy metals or radionuclides from an aqueous solution comprising a modified clinoptilolite, and methods of using same are provided.

Abstract: A process for fluoride removal from wastewater streams produced during industrial operation for further industrial use or to comply with environmental regulations. The process segregates the removal of fluoride and fluorosilicate ions, from the totality of ions in the waste water stream, thus improving treatment efficiency and reducing costs. Ion-exchange chromatography is used to remove the fluoride and fluorosilicate ions by passing the wastewater stream through one or more columns that contain a charged resin which selectively binds cations/anions in the stream. The fluoride ions are washed from the column and then collected for removal or use in other processes.

Abstract: A multicolumn selectivity inversion generator separation method has been developed in which a desired daughter radionuclide is selectively extracted from a solution of the parent and daughter radionuclides by a primary separation column, stripped, and passed through a second guard column that retains any parent or other daughter impurities, while the desired daughter elutes. This separation method minimizes the effects of radiation damage to the separation material and permits the reliable production of radionuclides of high chemical and radionuclidic purity for use in diagnostic or therapeutic nuclear medicine.

Abstract: The liquid effluent from solvent extraction contains radioactive thorium Th-231 and Th-234. This invention uses an ion exchange process to remove and concentrate the thorium. The process is designed so that the thorium remains on the ion exchange column until it decays to uranium and protactinium. These decay products are subsequently replaced by additional thorium. Therefore, the thorium never reaches break-through and the column can be used continuously without regeneration.

Abstract: A decontamination system uses magnetic molecules having ferritin cores to selectively remove target contaminant ions from a solution. The magnetic molecules are based upon a ferritin protein structure and have a very small magnetic ferritin core and a selective ion exchange function attached to its surface. Various types of ion exchange functions can be attached to the magnetic molecules, each of which is designed to remove a specific contaminant such as radioactive ions. The ion exchange functions allow the magnetic molecules to selectively absorb the contaminant ions from a solution while being inert to other non-target ions. The magnetic properties of the magnetic molecule allow the magnetic molecules and the absorbed contaminant ions to be removed from solution by magnetic filtration.

Abstract: The natural ability of an aquifer formation to remove radionuclides from ground water is recharged by injecting a leaching solution a well. The leaching solution replaces the radionuclides at natural sorption sites in the aquifer formation with ions that can be displaced subsequently by other radionuclides in the ground water. The leaching solution remains in the aquifer formation for a given period of time after which it is pumped out through the well. Thereafter, as water is pumped from the well, other radionuclides become lodged at the sorption sites in the aquifer formation thus being removed from the water.

Abstract: An object of the present invention is to provide a structure of a metal collecting material for use in seawater or river water or industrial wastewater to give the most excellent adsorption efficiency. Another object of the present invention is to provide a process for efficiently separating and recovering valuable metals or noxious metals from a metal collecting material having collected said valuable metals from seawater or noxious metals from river water or wastewater with the least possible waste generation. A metal collector according to an aspect of the present invention is formed by stacking at least partially alternate layers of a fibrous metal collecting material with a spacer for introducing a liquid to be treated into said collecting material, wherein the area of spacer side faces represents 25-75% of the total area of collecting material side faces and spacer side faces in the side faces of the stack.

Abstract: A multicolumn selectivity inversion generator has been developed in which bismuth-213 is selectively extracted from an HCl solution of the actinium-225 parent (and its radiogenic descendents) by a primary separation column containing a separation medium containing a neutral oxygenated organophosphorus extractant. After rinsing with dilute HCl, the bismuth-213 is stripped with a buffered NaCl solution. The stripped solution is passed through a cation-exchange resin guard column that retains the actinium-225 and radium-225 contaminants while the bismuth-213 elutes. This generator method minimizes the unpredictable effects of radiation damage to the support material and permits the reliable production of bismuth-213 of high chemical and radionuclidic purity.

Abstract: A method of separation and recovery of elements from radioactive liquid wastes, includes a step of bringing into contact a high-level radioactive liquid waste containing separation target elements including Americium, Curium, Zirconium, Molybdenum, Palladium and rare earth elements with solid absorbent containing organophosphorus compounds so that the separation target elements are absorbed in the solid absorbent, a step of bringing into contact the solid absorbent with an acidic solution containing diethylenetriaminepentaacetic acid so that Americium, Curium, Zirconium, Molybdenum, Palladium and heavy rare earth elements are eluted from the solid absorbent, and a step of bringing into contact the solid absorbent underwent the first elution step with water or dilute nitric acid so that light rare earth elements are eluted from the solid absorbent.

Abstract: A method for removing heavy metals or radionuclides from an aqueous solution comprising contacting the aqueous solution with an ion exchange material selected from a solid ion exchange material, a liquid ion exchange material, or mixtures thereof, wherein the ion exchange material is prepared by the process comprising: contacting clinoptilolite with an alkaline solution at a temperature of about 85° C. to about 300° C. and for a sufficient time to form a treated slurry comprising a solid fraction and a liquid fraction, and optionally separating the solid fraction from the treated slurry and washing the solid fraction to produce the solid ion exchange material; and optionally recovering the liquid fraction of the treated slurry to produce the liquid ion exchange material. A process for producing the above ion exchange materials useful for removing heavy metals or radionuclides from an aqueous solution, and the solid and liquid ion exchange materials produced by the process.

Abstract: A method, composition, and apparatus for removing contaminant species from an aqueous medium comprising: providing a material to which zirconium has been added, the material selected from one or more of zeolites, cation-exchangeable clay minerals, fly ash, mesostructured materials, activated carbons, cellulose acetate, and like porous and/or fibrous materials; and contacting the aqueous medium with the material to which zirconium has been added. The invention operates on all arsenic species in the form of arsenate, arsenite and organometallic arsenic, with no pretreatment necessary (e.g., oxidative conversion of arsenite to arsenate).

Abstract: An injection and solidification operation as well as a kneading and solidification operation can be performed by a single facility. A decreased amount of radioactive secondary waste is generated. A solidifying agent paste is prepared by kneading a solidifying agent and additive water. The solidifying agent paste is injected into a solidifying container. The radioactive waste is charged into the solidifying container and kneaded.

Abstract: The recovery of nickel, cobalt and other metals by phytomining is described. Plants of the Alyssum genus are grown in nickel rich soil. The uptake of nickel is enhanced by maintaining specific soil conditions, including a concentration of calcium between (but not including) 0.128 mM an 5.0 mM and an acidic pH. Ni uptake may be further enhanced by maintaining a ratio of exchangeable Ca/Mg of 0.16-0.40. Uptake may be further enhanced by addition of chelating agents and ammonium based fertilizers.

Abstract: A gas-free system for separating a solution of substantially impurity-free daughter products from an associated parent load solution includes a pump, a plurality of multi-port valves, separation medium and a processor. An uncoiled conduit extends between a third port of a second multi-port valve and a first multi-port valve. A processor is operably coupled to a pump, and the plurality of multi-port valves. A method for separating a solution of substantially impurity-free daughter product from an associated parent load solution is also disclosed.

Abstract: A solid ion-exchange material useful for removing heavy metals or radionuclides from an aqueous or gaseous solution comprising a modified clinoptilolite, and methods of using same are provided.

Abstract: A process for removing uranium/vanadium-based contaminants from groundwater using a primary in-ground treatment media and a pretreatment media that chemically adjusts the groundwater contaminant to provide for optimum treatment by the primary treatment media.

Abstract: A solid ion-exchange material useful for removing heavy metals or radionuclides from an aqueous solution comprising a modified clinoptilolite, and methods of using same are provided.

Abstract: A method for removing heavy metals or radionuclides from an aqueous solution comprising contacting the aqueous solution with an ion exchange material selected from a solid ion exchange material, a liquid ion exchange material, or mixtures thereof, wherein the ion exchange material is prepared by the process comprising: contacting clinoptilolite with an alkaline solution at a temperature of about 85° C. to about 300° C. and for a sufficient time to form a treated slurry comprising a solid fraction and a liquid fraction, and optionally separating the solid fraction from the treated slurry and washing the solid fraction to produce the solid ion exchange material; and optionally recovering the liquid fraction of the treated slurry to produce the liquid ion exchange material. A process for producing the above ion exchange materials useful for removing heavy metals or radionuclides from an aqueous solution, and the solid and liquid ion exchange materials produced by the process.

Abstract: The invention provides a use of a material comprising antimony silicate as a sorbent in the removal of metal ions, e.g. radioactive metal ions, from an acidic liquid medium. The metal ions may be selectively removed from amongst other ions such as Na, K, Mg, and Ca ions. Strontium is particularly effectively removable in this way. There is also provided a method of preparing an antimony silicate material for use in removing metal ions. The invention further provides a material comprising antimony silicate doped with one or more elements selected from the group consisting of tungsten, niobium and tantalum. The doped material has been found to be particularly effective as a sorbent in the removal of metal ions from a liquid medium.

Abstract: Inorganic-organic hybrid gels can be employed to extract chemical species such as lanthanides and actinides and their preparation. The gels include a network of inorganic components with the formula: where M is Si, Ti, Zr or Al, wherein organic molecules which can complex the species to be extracted are integrated, with each organic molecule being covalently linked to one or several M atoms in the network. The network is made by a sol-gel process from metallic alkoxides functionalized with complexing groups (amino, ether, hydroxy, amido, pyridino and bipyridino), capable of extracting metals such as lanthanides and actinides.

Abstract: A method for removing a wide variety of radioactive contaminants from a contaminated surface sufficient for the surface to be classified as a low-level waste or as free release. Contaminated surfaces may be classified as Class C, Class B, Class A, or high-level radioactive wastes prior to treatment. An aqueous solution having a wetting agent and a complex substituted keto-amine is provided. The aqueous solution is left on the surface for a time sufficient to remove the radioactive contaminants into the aqueous solution which is then removed. Depending on the type and condition of the surface, an acid may be added to the aqueous solution to aid in the contaminant removal process. However, typical metals surfaces may often be treated effectively without the use of concentrated acids or with dilute concentrations of such acids. The method of the present invention has the effect of removing substantially all of the radioactive contaminants from a variety of previously contaminated surfaces.

Abstract: A method for removing radioactive contaminants from a given surface. An aqueous solution having a wetting agent and a complex substituted keto-amine is provided. The solution is left on the surface for a time sufficient to remove the radioactive contaminants into the aqueous solution which is then removed. Depending on the type and condition of the surface, a concentrated acid may be added to the aqueous solution to aid in the contaminant removal process. In such a case, a pH of less than 3.0, and preferably less than 1.5 is maintained. If a concentrated acid is used, the acidic solution containing radioactive contaminants is preferably neutralized by an alkaline material to a pH of between 5.5 and 9.0. Removal of thorium contamination from railcars is one useful application of the invention. The method of the present invention has the effect of removing substantially all of the radioactive contaminants from a previously contaminated surface.

Abstract: A method for purifying contaminated water involves passing contaminated water through a porous bed of steel slag. The steel slag can be used to remove various contaminants or reduce the concentration of such contaminants, such as heavy metals (for example, hexavalent chromium), chlorinated organic compounds, and certain inorganic anions. The method preferably involves placing an underground barrier of a porous bed of steel slag in a flow path of contaminated groundwater then allowing contaminated groundwater to pass through the barrier to purify the contaminated groundwater. The slag particles may be used as produced with no further grinding necessary, although the slag may be passed through a sieve or sieves to obtain a set of slag particles having a median diameter of about ⅛ inch to 1 inch, and preferably between about ¼ inch to ⅜ inch. Due to the inherent permeability of slag, no additive need be mixed with the slag.

Abstract: The present invention provides a generator capable of producing therapeutic Bismuth-213 doses. Also disclosed are methods of preparing Bismuth-213-labeled compounds using such generator and applications of the labeled compounds.

Abstract: A gas-free system for separating a solution of substantially impurity-free daughter products from an associated parent load solution includes a pump, a plurality of multi-port valves, separation medium and a processor. An uncoiled conduit extends between a third port of a second multi-port valve and a first multi-port valve. A processor is operably coupled to a pump, and the plurality of multi-port valves. A method for separating a solution of substantially impurity-free daughter product from an associated parent load solution is also disclosed.

Abstract: The invention relates to a composite solid material fixing mineral contaminants, with a metal hexacyanoferrate basis, characterised in that it comprises a solid support coated with a pellicle of an anion-exchange polymer to which is fixed an insoluble metal hexacyanoferrate forming a thin layer. The present invention also relates to the method of preparing the said composite solid material fixing mineral contaminants with a hexacyanoferrate basis. The present invention finally relates to method of fixing, which can be carried out in a column and continuously, of at least one mineral contaminant contained in a solution, on the said composite solid material fixing mineral contaminants. The said solution is in particular a liquid or an effluent originating from the nuclear industry and installations.

Abstract: This invention relates to an apparatus for removing solutes from a solution using a nano-filtration means to provide a treated solution.

Abstract: A system for remediating groundwater contaminated with radionuclides, consisting of an underground bed of crushed zeolites. Distribution pipes convey contaminated groundwater to the zeolite bed by means of a pump, which draws the contaminated water through wells from an underground plume of released waste mixed with groundwater. The radionuclides in the water undergo capture with the zeolite minerals and lock into the zeolite crystal lattice. After the contaminated water passes through the zeolite bed, it is collected by a series of collection pipes and conveyed to a sampling station, where it can be determined whether the water has been decontaminated sufficiently to discharge it by piping to a river outfall or back to the ground. When functioning, the system contains the released contaminants on the waste site and prevents further spread and migration of the contaminated water by means of the cone of depression created by the pumping well.

Abstract: An extractant medium for extracting alkaline earth cations from an aqueous acidic sample solution is described as are a method and apparatus for using the same. The separation medium is free of diluent, free-flowing and particulate, and comprises a Crown ether that is a 4,4′(5′)[C4-C8-alkylcyclohexano]18-Crown-6 dispersed on an inert substrate material.

Abstract: The liquid effluent from solvent extraction contains radioactive thorium Th-231 and Th-234. This invention uses an ion exchange process to remove and concentrate the thorium. The process is designed so that the thorium remains on the ion exchange column until it decays to uranium and protactinium. These decay products are subsequently replaced by additional thorium. Therefore, the thorium never reaches break-through and the column can be used continuously without regeneration.

Abstract: A method for removing radioactive contaminants from a given surface. An acidic solution having a pH of less than 3.0, and preferably less than 1.5, of a complex substituted keto-amine, and a mixture of a saturated and unsaturated lower alcohol (e.g. isopropyl alcohol and propargyl alcohol), and concentrated acid is applied to a contaminated surface. The solution is left on said surface for a time sufficient to remove the radioactive contaminants into the acidic solution and then removed. The acidic solution containing the radioactive contaminants is preferably neuralized by an alkaline material to a pH of between 5.5 and 9.0. Removal of thorium contamination from railcars is one useful application of the invention. The method of the present invention has the effect of removing substantially all of the radioactive contaminants from a previously contaminated surface.

Abstract: A new microporous crystalline molecular sieve material having the formula Cs3TiSi3O95•3H2O and its hydrothermally condensed phase, Cs2TiSi6O15, are disclosed. The microporous material can adsorb divalent ions of radionuclides or other industrial metals such as chromium, nickel, lead, copper, cobalt, zinc, cadmium, barium, and mercury, from aqueous or hydrocarbon solutions. The adsorbed metal ions can be leached out for recovery purposes or the microporous material can be hydrothermally condensed to a radiation resistant, structurally and chemically stable phase which can serve as a storage waste form for radionuclides.

Abstract: The liquid effluent from solvent extraction contains radioactive thorium Th-231 and Th-234. This invention uses an ion exchange process to remove and concentrate the thorium. The process is designed so that the thorium remains on the ion exchange column until it decays to uranium and protactinium. These decay products are subsequently replaced by additional thorium. Therefore, the thorium never reaches break-through and the column can be used continuously without regeneration.

Abstract: Methods, compositions and devices for purifying polypeptides and/or proteins using metal loaded ligand bound membranes by metal ion affinity chromatography are described.

Abstract: A process for modifying a medium is disclosed that includes treating a medium having a metal ion sorption capacity with a solution that includes: A) an agent capable of forming a complex with metal ions; and B) ions selected from the group consisting of sodium ions, potassium ions, magnesium ions, and combinations thereof, to create a medium having an increased capacity to sorb metal ions relative to the untreated medium.

Abstract: A process based on ion exchange with separated beds is disclosed for the deionization of substances that are not stable in the presence of strongly acidic cation exchangers, wherein the solution to be deionized is contacted with a first bed consisting of a basic anion exchanger in the form of hydrogen carbonate and subsequently with a second bed, connected in series, consisting of a weakly acidic cation exchanger in hydrogen form.

Abstract: Compositions and methods for selectively binding metal ions from a source solution comprise using a polyhydroxypyridinone-containing ligand covalently bonded to a particulate solid support through a hydrophilic spacer of the formula SS-A-X-L (HOPO)n where SS is a particulate solid support such as silica or a polymeric bead, A is a covalent linkage mechanism, X is a hydrophilic spacer grouping, L is a ligand carrier, HOPO is a hydroxypyridinone appropriately spaced on the ligand carrier to provide a minimum of six functional coordination metal binding sites, and n is an integer of 3 to 6 with the proviso that when SS is a particulate organic polymer, A-X may be combined as a single covalent linkage.

Abstract: A process for removing dissolved uranium from water is provided. The process basically comprises (a) mixing phosphoric acid or particulate bone ash with the water, (b) mixing calcium hydroxide with the mixture produced in step (a) to thereby form calcium hydroxy phosphate or calcium hydroxy apatite which reacts with and complexes at least a portion of the uranium in the water to form a precipitate thereof, and (c) separating the precipitate from the water.

Abstract: The invention relates to adsorption material for radionuclides based on a fine fibrous material containing chitin. The material is obtained from fungi and insoluble ferrocyanides of the transition metals, especially copper ferrocyanide. The adsorption material is especially well suited for cleaning liquid radioactive wastes produced in the atomic industry and by nuclear power stations.

Abstract: A wastewater treatment system and process for removal of radioactive particulates includes continuous monitoring of charged particles and the addition of chemicals to coagulate and cause removal of the particulates from the wastewater.

Abstract: The present invention provides a novel process for the removal and recovery of radionuclides from waste waters and process streams. The process of the present invention utilizes a combination of a supported liquid membrane (SLM) and a strip dispersion to improve extraction of the target species while increasing membrane stability and reducing processing costs. Additionally, the invention provides a family of new extractants, alkyl phenylphosphonic acids, for the removal and recovery of radionuclides and/or metals, including the use of the new extractants in the process. The new extractant selectively removes radionuclides and metals from the feed stream to provide a concentrated strip solution of the target species.

Abstract: A process for chemical fixation of radionuclides and radioactive compounds present in soils, solid materials, sludges and liquids. Radionuclides and other radioactive compounds are converted to low-temperature Apatite-Group structural isomorphs (general composition: (AB)5(XO4)3Z), usually phosphatic, that are insoluble, non-leachable, non-zeolitic, and pH stable by contacting with a sulfate, hydroxide, chloride, fluoride and/or silicate source and with a phosphate anion in either a one or two step process. The Apatitic-structure end product is chemically altered from the initial material and reduced in volume and mass. The end product can be void of free liquids and exhibits sufficiently high levels of thermal stability to be effective in the presence of heat generating nuclear reactions. The process occurs at ambient temperature and pressure.

Abstract: Compositions and methods for selectively binding metal ions from a source solution comprise using a polyhydroxypyridinone-containing ligand covalently bonded to a particulate solid support through a hydrophilic spacer of the formula SS-A-X-L(HOPO)n, where SS is a particulate solid support such as silica or a polymeric bead, A is a covalent linkage mechanism, X is a hydrophilic spacer grouping, L is a ligand carrier, HOPO is a hydroxypyridinone appropriately spaced on the ligand carrier to provide a minimum of six functional coordination metal binding sites, and n is an integer of 3 to 6 with the proviso that when SS is a particulate organic polymer, A-X may be combined as a single covalent linkage.

Abstract: A method for removal of cesium from aqueous solution, particularly from nuclear waste liquids. The cesium-containing aqueous solution is contacted with a solid-state hexacyanoferrate compound of a transition element for binding cesium to the hexacyanoferrate. The aqueous solution of reduced cesium content is separated from the hexacyanoferrate. Preferably, a nickel or cobalt hexacyanoferrate is utilized having a fraction of exchangeable transition elements smaller than 35 %. The hexacyanoferrate compound of said transition element may be produced by slowly adding an aqueous solution of the hexacyanoferrate into the transition element salt solution, the concentration of the transition element salt solution being at least 0.35 mol/l, stirring the mixture at ambient temperature during the addition, and separating and recovering the resulting hexacyanoferrate precipitate from the mixture.

Abstract: The present invention provides a method for preparing [F-18]-fluoride ion which comprises the step of bringing [O-18]-enriched water containing [F-18]-fluoride ion formed by proton irradiation of [O-18]-enriched water into contact with a strongly acidic cation exchange resin to remove impurity cations, the step of then bringing the [O-18]-enriched water containing [F-18]-fluoride ion treated above into contact with a weakly basic anion exchange resin to make [F-18]-fluoride ion adsorbed to the resin and, along therewith, to recover the [O-18]-enriched water which has passed through the resin, and the step of eluting and collecting the [F-18]-fluoride ion adsorbed to the weakly basic anion exchange resin.

Abstract: A method for removing low levels of heavy metal from chemical/industrial waste streams containing interfering anions which typically form strong complexes with heavy metals such as uranium utilizes an ion exchange resin having amino-phosphonic functional groups which selectively capture the heavy metal from the chemical waste stream in an efficient manner such that the amount of heavy metal in the waste stream is reduced to sub-ppm levels. After capture, the resin is treated with a sequestering agent, such as a solution of ammonium fluoride or ammonium sulfate, which releases the heavy metal from the resin. The resin is then regenerated with a sodium solution and returned to service. Utilizing ion exchange and a resin containing amino-phosphonic functional groups allows removal of heavy metal to a level of less than or equal to 0.1 ppm which is a substantial reduction in view of the presence of significant quantities of complexing anions in the waste stream.

Abstract: A composition of matter is provided in which a phosphonic acid or phosphonic acid ester group is linked through a thioether residue to a silicon atom which is further covalently bonded to a solid inorganic support. The compositions can be employed to selectively separate metal ions having high cationic charge from a solution containing lower-charged cations, and also to selectively separate highly charged cations having a relatively high charge density from cations having the same charge, but a lower charge density.

Abstract: A process for producing substantially radio-impurity-free Bi-212 is disclosed. An acidic feed solution containing Pb-212 is contacted with an extraction medium to bind the Pb-212 thereto. The extraction medium is rinsed with a second acid solution to remove impurities therefrom, leaving a substantially impurity-free Pb-212-laden extraction medium The Pb-212 grows on the extraction medium to form Bi-212 by radioactive decay. The Bi-212 is then eluted from the extraction medium with an acid solution to form a substantially radio-impurity-free Bi-212 acid solution. An apparatus for carving out this process and a process for the therapeutic use thereof are also disclosed.

Abstract: A fluid stream has material selected from the group consisting of radioactive matter and metals removed from it. An example material to be removed is cesium ions. A silico-titanate composition have a mole ratio of Si:Ti of 0.01:1.7 is provided in the fluid stream. The material to be removed is them permitted to bind to the silico-titanate composition. The silico-titanate composition may include a metal dopant MD present in a mole ratio of MD:Ti up to 1.0. The silico-titanate may also be a cation M present in a mole ratio of M:Ti up to 2.0.

Abstract: A process based on ion exchange with separated beds is disclosed for the deionization of substances that are not stable in the presence of strongly acidic cation exchangers, wherein the solution to be deionized is contacted with a first bed consisting of a basic anion exchanger in the form of hydrogen carbonate and subsequently with a second bed, connected in series, consisting of a weakly acidic cation exchanger in hydrogen form.