Abstract: Disclosed herein are a class of anion exchange resins containing two different exchange sites with improved selectivity and sorptive capability for chemical species in solution, such as heptavalent technetium (as pertechnetate anion, TcO.sub.4.sup.-). The resins are prepared by first reacting haloalkylated crosslinked copolymer beads with a large tertiary amine in a solvent in which the resin beads can swell, followed by reaction with a second, smaller, tertiary amine to more fully complete the functionalization of the resin. The resins have enhanced selectivity, capacity, and exchange kinetics.

Abstract: A portable point of use water decontaminating unit adapted to receive a flow of water from a faucet or other water source and pass the water through a filtering and decontaminating system to deliver the water as a continuous flow to an outlet. There is a pressure regulator to deliver the water at a proper volumetric flow rate, a pre-disinfectant filter system to receive the water from the pressure regulator and a post disinfectant filter section to filter the disinfectant and contaminants from the water. There is a disinfectant section comprising a disinfectant injector, and an elongate residence tube extending in successive coils around the interior of the container to receive the water from the disinfectant injection means and accomplish disinfection as the water travels through the residence tube.

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).sub.5 (XO.sub.4).sub.3 Z), 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: A method for removing metal ions from solution comprises the steps of providing titanate particles by spray-drying a solution or slurry comprising sorbent titanates having a particle size up to 20 micrometers, optionally in the presence of polymer free of cellulose functionality as binder, said sorbent being active towards heavy metals from Periodic Table (CAS version) Groups IA, IIA, IB, IIB, IIIB, and VIII, to provide monodisperse, substantially spherical particles in a yield of at least 70 percent of theoretical yield and having a particle size distribution in the range of 1 to 500 micrometers. The particles can be used free flowing in columns or beds, or entrapped in a nonwoven, fibrous web or matrix or a cast porous membrane, to selectively remove metal ions from aqueous or organic liquid.

Abstract: Hazardous compounds are chemically treated to remove various pollutants by subjecting the compounds (samples) to various process steps, including selecting specific solvents and using them, treating the sample at room temperature or below (30.degree. C. or lower); separating fatty acids mixed with heavy metal and semi-metal compounds as well as the separation of organic substances (including halogenated compounds) added to heavy metals and semi-metals; and using sodium nitrite and sodium 1-naphthylamine-4-sulfonate in combination from specific solvents, thereby in the sample, adsorbing and fixating halogen substances related to air pollution, coagulation resulting from the decomposition of fatty acids and the fixation of such compounds by quicklime and graphite and the stable fixation of heavy-metal oxide and semi-metal compounds using solvents having redox action and the formation of their complex salts and compounds, the above being accomplished by a continuous processing method.

Abstract: The present invention provides methods for producing a photoresist having a very low level of metal ions, utilizing a treated chelating ion exchange resins to make the neutral ammonium salt or acid form. A method is also provided for producing semiconductor devices using such photoresist compositions.

Abstract: A method and a device are provided for disposing of an aqueous solution that contains an organic acid and an iron complex and occurs particularly in the decontamination of radioactively contaminated surfaces of components. It is contemplated that the iron complex in the solution is reduced by irradiation with UV light. A dissolved iron salt and carbon dioxide, which is given off, are formed in the process. An oxidant is then added to the solution that contains the dissolved iron salt and the organic acid. This produces water, and the iron complex forms once again. Some of the dissolved iron salt is removed from the solution by means of a cation exchanger. The solution containing the iron complex is irradiated again with UV light. A cycle process ensues, which continues until all the organic acid is consumed.

Abstract: A process for treating oils and solvents contaminated by radioactive substances includes a step of subjecting the oils and solvents to the action of pre-selected micro-organisms in the presence of air and a very large volume of water, relative to the volume of oils and solvents to be treated. The micro-organisms destroy organic molecules, and in particular transform them into CO.sub.2 and H.sub.2 O. Further steps of the process include preparing a predetermined volume of water having predetermined characteristics of dissolved oxygen concentration, pH and redox potential and adding a predetermined charge of oils and solvents contaminated by radioactive substances to this volume of water, the charge corresponding to a volume of oils and solvents which is a predetermined fraction of the predetermined volume of water. The charge is subjected to the action of micro-organisms at a predetermined temperature and for a predetermined time period.

Abstract: A method comprises the step of spray-drying a solution or slurry comprising (alkali metal or ammonium) (metal) hexacyanoferrate particles in a liquid, to provide monodisperse, substantially spherical particles in a yield of at least 70 percent of theoretical yield and having a particle size in the range of 1 to 500 micrometers, said particles being active towards Cs ions. The particles, which can be of a single salt or a combination of salts, can be used free flowing, in columns or beds, or entrapped in a nonwoven, fibrous web or matrix or a cast porous membrane, to selectively remove Cs ions from aqueous solutions.

Abstract: The invention relates to a method for separating metals present in a solution using chitosane. According to the present invention, chitosane in modified physical form is used which allows faster, more extensive fixation of the metals present in a solution. This purpose is achieved using a method in which the chitosane used is a lyophilizate of chitosane, in particular a lyophilizate of chitosane salt.

Abstract: The invention relates to crown calix.vertline.4.vertline.arenes, their preparation process and their use for the selective extraction of cesium and actinides. These crown calixl4larenes comply with the formula: ##STR1## in which R.sub.1 represents a group of formula X(C.sub.2 H.sub.4 X).sub.m and X(C.sub.2 H.sub.4 X).sub.n YX(C.sub.2 H.sub.4 X).sub.n with X=O or N(R.sub.4), m=3, 4, 5 or 6, Y=cycloalkylene or arylene and n=1, 2 or 3. These crown.vertline.4.vertline.arenes, whose benzene nuclei are optionally substituted by alkyl groups, can be used as extractants, e.g. in liquid membrane form, for separating cesium from acid solutions containing sodium in a large quantity compared with the cesium quantity, e.g. irradiated fuel reprocessing plant effluents.

Abstract: The present invention discloses a method of creating a monolithic wasteform consisting of a binder which chemically immobilizes heavy metals and radioactive materials so as to render them environmentally safe. An apatite or apatite-like material may be employed in immobilizing the hazardous material. A preferred practice of the invention employs a hydroxyapatite or a calcium depleted hydroxyapatite into which the waste materials are substituted and immobilized. The stoichiometric apatite or calcium deficient hydroxyapatite may be formed in the aqueous solution containing heavy metals or radioactive materials, or both, wherein binding of the latter is effected. Alternatively, a preformed calcium deficient phosphate may be introduced into the solution having heavy metals or radioactive materials, or both, dissolved therein in effecting the desired binding in situ. A high strength monolithic wasteform which may be stored or buried for long-term, safe storage of the hazardous materials is produced.

Abstract: A method for removing a selected heavy metal ion from an aqueous solution is provided herein. Said method comprises contacting the solution with collophane at a pH effective for capture of the selected heavy metal ion by the collophane. Heavy metal ions include Sb.sup.2+, As.sup.3+, Cd.sup.2+, Cr.sup.3+, Co.sup.2+, Cu.sup.2+, Fe.sup.3+, Pb.sup.2+, Mn.sup.2+, Hg.sup.2 +, UO.sub.2.sup.2+ or Zn.sup.2+, preferably Fe.sup.3+, Pb.sup.2+, and Hg.sup.2+, As.sup.3+ and UO.sub.2.sup.2+. The process is pH-sensitive and selective removal of desired heavy metal ions may be achieved by varying pH and other conditions to favor removal of the desired ions and leave other heavy metal ions whose removal is inhibited under such conditions in solution.

Abstract: A crown ether cesium ion extractant is disclosed as is its synthesis. The crown ether cesium ion extractant is useful for the selective purification of cesium ions from aqueous acidic media, and more particularly useful for the isolation of radioactive cesium-137 from nuclear waste streams. Processes for isolating cesium ions from aqueous acidic media using the crown ether cesium extractant are disclosed as are processes for recycling the crown ether cesium extractant and processes for recovering cesium from a crown ether cesium extractant solution.

Abstract: Treatment compositions and a method are provided for the removal of a plurality of heavy metals and radioactive isotopes from wastewater. The treatment compositions comprise an alkali; adsorbents, such as montmorillonite and illite clays; catalysts, such as polyelectrolytes and sodium carbonate; one or more flocculants, such as a metal salt and calcium hydroxide; zirconium as a chelating and complexing agent; and boron as a neutron absorbent. The selected composition is introduced into and mixed with the wastewater, which is then filtered to produce a sludge containing the contaminants.

Abstract: A method for immobilizing waste chlorides salts containing radionuclides and hazardous nuclear material for permanent disposal, and in particular, a method for immobilizing waste chloride salts containing cesium, in a synthetic form of pollucite. The method for synthesizing pollucite from chabazite and cesium chloride includes mixing dry, non-aqueous cesium chloride with chabazite and heating the mixture to a temperature greater than the melting temperature of the cesium chloride, or above about 700.degree. C. The method further comprises significantly improving the rate of retention of cesium in ceramic products comprised of a salt-loaded zeolite by adding about 10% chabazite by weight to the salt-loaded zeolite prior to conversion at elevated temperatures and pressures to the ceramic composite.

Abstract: A process for the production of radiostrontium consists in that a target of metallic rubidium is bombarded by a flow of accelerating charged particles. The target of irradiated rubidium is melted, whereas the extraction of radiostrontium is carried out by sorption on the surface of a sorbing material immersed into the irradiated molten metallic rubidium. As the sorbing material, use is made of materials selected from the group consisting of heat-resistant metals or metallic oxides or silicon which are inert with respect to rubidium. The resultant radiostrontium is extracted from the irradiated rubidium. The temperature of the sorbing material is selected to be close to the optimum one for the sorption of radiostrontium which is within the range of from the melting point of metallic rubidium to 220.degree. C. And the temperature of molten rubidium is selected to be close to the optimum one for the desorption of radiostrontium within the range of from 220.degree. C. to 270.degree. C.

Abstract: A method for reducing radioactive waste, particularly oils and solvents in nuclear power stations and military research centers, and a device therefor. The method comprises feeding the waste into a tank (1) in which it is continuously stirred, preheating the waste, performing a chemical precipitation treatment, feeding the mixture into a centrifuge (2), performing an electrostatic or conventional filtration step, and testing the level of radioactivity. The treatment is continuously repeated until the desired level of decontamination is reached.

Abstract: A process for preconcentrating and separating radium from a contaminated solution containing at least water and radium includes the steps of adding a quantity of a water-soluble macrocyclic polyether to the contaminated solution to form a combined solution. An acid is added to the combined solution to form an acidic combined solution having an ?H.sup.+ ! concentration of about 0.5M. The acidic combined solution is contacted with a sulfonic acid-based strong acid cation exchange medium or a organophilic sulfonic acid medium having a plurality of binding sites thereon to bind the radium thereto and to form a radium-depleted solution. The radium-depleted solution is separated from the strong acid cation exchange medium or organophilic sulfonic acid medium. The radium remaining bound to the exchange medium or organophilic reagent is then stripped from the exchange medium or organophilic medium and the activity of the radium is measured.

Abstract: A process for removing contaminant metal ions from a liquid stream is disclosed. The process involves contacting the liquid stream with a crystalline molecular sieve which has a crystal structure which is an intergrowth of the pharmacosiderite and sitinakite structures. The molecular sieve has an empirical formula of:A.sub.((4-4x)(n) (M.sub.x Ti.sub.1-z Ge.sub.y).sub.4 (Ge.sub.1-p Si.sub.p).sub.q O.sub.rwhere A is a cation such as sodium or potassium and M is a metal such as niobium or tantalum. These molecular sieves are particularly effective in removing cesium and strontium ions from aqueous streams.

Abstract: A process and apparatus for separating tritium from an aqueous solution that contains one or more additional dissolved radionuclides is disclosed. In accordance with the process the aqueous solution as a first liquid phase is contacted with each of three layers as a solid phase within a column. A first layer comprises particles having a plurality of pendent methylene diphosphonate groups. A second layer comprises strongly basic anion exchange particles, and a third layer comprises polymer particles free of ionically charged groups. The contact is maintained until a second liquid phase is formed that contains tritium as substantially the only radionuclide, and that second liquid phase is collected and can then be counted to determine the amount of tritium present. The column with its three layers constitutes the separation apparatus.

Abstract: A process for producing substantially impurity-free Bi-213 cations is disclosed. An aqueous acid feed solution containing Ac-225 cations is contacted with an ion exchange medium to bind the Ac-225 cations and form an Ac-225-laden ion exchange medium. The bound Ac-225 incubates on the ion exchange medium to form Bi-213 cations by radioactive decay. The Bi-213 cations are then recovered from the Ac-225-laden ion exchange medium to form a substantially impurity-free aqueous Bi-213 cation acid solution. An apparatus for carrying out this process is also disclosed.

Abstract: A process for the decontamination of radioactive materials which process comprises the steps of: i) contacting the material to be decontaminated with a dilute carbonate containing solution in the presence of ion exchange particles which either contains or have a chelating function bond to them; and ii) separating the ion exchange particles from the dilute carbonate containing solution. The radioactive materials which are treated may be natural materials, such as soil, or man-made materials such as concrete or steel, which have been subjected to contamination.

Abstract: Although a chelating agent solution having radioactive contaminants is solidified by mixing with cement and then stored, a vast storage place is required for storing an enormous amount of chelating agent solution. When such a chelating agent solution is treated with an ion-exchange resin, a large amount of ion-exchange resin is required, and a large amount of ion-exchange resin having radioactive contaminants is produced. The present invention thus provides a method of treating a chelating agent solution having radioactive contaminants, which can significantly decrease the amount of the chelating agent solution having radioactive contaminants, and which, when an ion-exchange resin is used, can significantly decrease the load on the ion-exchange resin without producing a large amount of ion-exchange resin having radioactive contaminants.

Abstract: A composite material useful for removing heavy metal ions from solutions such as aqueous waste streams comprises a ceramic inorganic support such as silica gel which is covalently bonded, through a silane coupling agent, to a hydroxyquinoline ligand or such a support which has been reacted with a silylating agent and then on which is deposited a hydroxyquinoline ligand.

Abstract: Composite materials useful for removing metal ions from solutions such as aqueous waste streams comprise an inorganic ceramic support such as silica gel that has active hydroxyl groups. The support is reacted with a silane linking compound or with a titanizing agent. A chelating compound, which can be a thiol or an amine, is attached to the silane or to titanium atoms of the titanized surface of the support.

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 labeledbiological molecules from liquid radioactive waste solutions.

Abstract: The present invention is a method for removing oxidized contaminant(s) from water. More specifically, the invention has the steps of contacting water containing the oxidized contaminant(s) with a layered aluminosilicate having Fe(II). The aluminosilicate may contain naturally occurring Fe(II), or the Fe(II) may be produced by reducing Fe(III) that is initially present. Reduction may be either by exposure to a chemical or biological reductant. Contacting the water containing oxidized contaminant(s) may be by (1) injection of Fe(II)-containing layered aluminosilicate, via a well, into a saturated zone where it is likely to intercept the contaminated water; (2) injection of contaminated water into a vessel containing the Fe(II)-bearing layered aluminosilicate; and (3) first reducing Fe(III) in the layered aluminosilicate to Fe(II) by injection of a biological or chemical reductant, into an aquifer or vessel having sufficient Fe(III)-bearing aluminosilicate to produce the necessary Fe(II).

Abstract: Novel ceramic compositions are used for removing metal ions by chelation from solutions such as aqueous waste streams. The compositions are formed by covalently bonding to terminal hydroxy groups of a ceramic inorganic carrier or support a substituted silane linking group attached to a chelating agent or ligand which is pyrogallol or a derivative thereof.

Abstract: A .sup.99 Mo/.sup.99m Tc generator system includes a sorbent column loaded with a composition containing .sup.99 Mo. The sorbent column has an effluent end in fluid communication with an anion-exchange column for concentrating .sup.99m Tc eluted from the sorbent column.A method of preparing a concentrated solution of .sup.99m Tc includes the general steps of:a. providing a sorbent column loaded with a composition containing .sup.99 Mo, the sorbent column having an effluent end in fluid communication with an anion-exchange column;b. eluting the sorbent column with a salt solution to elute .sup.99m Tc from the sorbent and to trap and concentrate the eluted .sup.99m Tc on the ion-exchange column; andc. eluting the concentrated .sup.99m Tc from the ion-exchange column with a solution comprising a reductive complexing agent.

Abstract: A method for separating .sup.213 Bi from a solution of radionuclides wherein the solution contains a concentration of the chloride ions and hydrogen ions adjusted to allow the formation of a chloride complex. The solution is then brought into contact with an anion exchange resin, whereupon .sup.213 Bi is absorbed from the solution and adhered onto the anion exchange resin in the chloride complex. Other non-absorbing radionuclides such as .sup.225 Ra, .sup.225 Ac, and .sup.221 Fr, along with HCl are removed from the anion exchange resin with a scrub solution. The .sup.213 Bi is removed from the anion exchange resin by washing the anion exchange resin with a stripping solution free of chloride ions and with a reduced hydrogen ion concentration which breaks the chloride anionic complex, releasing the .sup.213 Bi as a cation. In a preferred embodiment of the present invention, the anion exchange resin is provided as a thin membrane, allowing for extremely rapid adherence and stripping of the .sup.213 Bi.

Abstract: Mixed radioactive wastes, such as those that include a radioactive component and a dissolved salt component, are treated by directing the waste through at least one ion-exchange medium that binds at least a portion of the radioactive component. A liquid discharge stream from which the radioactive component has been separated, and which includes the dissolved salt component, is directed into a molten bath that causes at least a portion of at least one dissolved salt component of the liquid discharge stream to be reductively vaporized and thereby form at least one vaporized product. A gaseous discharge stream is generated by the molten bath that includes at least one vaporized product. In one specific embodiment, the mixed radioactive waste includes radioactive cesium as the radioactive component and sodium nitrate as the dissolved salt component.

Abstract: A method is provided for reducing the concentration of radioactive materials or other trace contaminants in fluids withdrawn from subterranean reservoirs and also fluids in reservoirs. The method involves deposition of sorbent solids including, but not limited to, fine ion exchange resins, within the reservoir matrix surrounding a production well to act as an in-situ filter for dissolved radionuclides or other contaminants present in reservoir pore waters. For this purpose, the sorbent solid is either a) precipitated within the reservoir matrix by the reaction of ions or molecules 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.

Abstract: A method of decontaminating a site of metals, particularly radioactive metals, is provided. The contaminated material is contacted with pulverized bone, which sorbs the metals from the contaminated material. The bone may be derived from any animals having bone, such as cattle. Prior to use, the organic compounds of the bone are removed, so that inorganic bone composed primarily of hydroxylapatite is obtained. The morphology of the bone, including its crystalline structure and porosity, is maintained. As an alternative to bone derived from animals, synthetic inorganic bone composed of hydroxylapatite and having a physical structure equivalent to animal-derived bone may be used.

Abstract: An adsorbent for radioactive nuclides incorporating fibrous activated carbon. The adsorbent includes fibrous activated carbon having good adsorption performance, inorganic fiber and inorganic binder. Therefore, the adsorbent exhibits good shape stability when it is formed into a molded piece, has good combustion performance, and is not liable to scattering of radioactive nuclides adsorbed thereon when it is incinerated.

Abstract: A sheet article for solid phase extraction or solid phase reaction comprises at least one sorptive polymer pulp, and optionally at least one of sorptive and reactive particulate. The article can be used in a method of separating an analyte from a fluid comprising the step of passing a fluid comprising an analyte through a sheet article comprising poly(p- or m-phenylenephthalamide) pulp, the pulp optionally having incorporated therein solid phase particulates, the sheet article being capable of isolating the analyte from the fluid.

Abstract: The invention relates to a process and an installation for the decontamination of radioactive nitric effluents containing strontium and sodium. According to this process, contacting takes place in 1 of the aqueous effluent with an organic phase incorporating a crown ether such as DCH18C6 and a diluent such as CHCl.sub.3, in order to selectively extract the strontium with respect to the sodium, followed by the reextraction of the strontium in an aqueous solution in 3, followed by fixing in 5 on a cation exchange resin. This leads to a high strontium decontamination level with a very high concentration factor.

Abstract: A method and apparatus for purifying contaminated water includes four subsystems for removing undissolved solids, precipitation and flocculation of dissolved solids, polishing or cation removal of dissolved solids, and metallurgical furnace treatment of the separated contaminants along with gas cleaning. A unique high density inorganic adsorbent, produced during the reducing atmosphere Waelz Kiln processing of iron, zinc, lead and cadmium rich Electric Arc Furnace dust, is used to raise the pH level of the contaminated water in the precipitation procedure and again as an adsorbent filter bed in a clear well extraction vessel used in the polishing step.

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 ion exchange 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: Anion exchange resins including at least two positively charged sites and a ell-defined spacing between the positive sites are provided together with a process of removing anions or anionic metal complexes from aqueous solutions by use of such resins. The resins can be substituted poly(vinylpyridine) and substituted polystyrene.

Abstract: Preparation and use of polymeric materials containing hydrophobic anions and plasticizers for extraction of cesium and strontium. The use of polymeric materials containing plasticizers which are solvents for hydrophobic anions such as derivatives of cobalt dicarbollide or tetraphenylborate which are capable of extracting cesium and strontium ions from aqueous solutions in contact with the polymeric materials, is described. The polymeric material may also include a synergistic agent for a given ion like polyethylene glycol or a crown ether, for removal of radioactive isotopes of cesium and strontium from solutions of diverse composition and, in particular, for solutions containing large excess of sodium nitrate.

Abstract: The present invention is directed to an analytic method for detecting trace elements in fluid solution. A cation exchange resin is packed with a radiolabelled exchange material having certain characteristics and replaces the trace element ions in the fluid which becomes labelled. The label is subsequently detected using sensitive and well known radiation detection methods.

Abstract: A method of radiochemical analysis having the steps of providing a solid phase extraction sheet material containing ion-specific sorptive or reactive particles in a porous matrix as carrier for the particles, and providing a fluid including an ion-containing radiochemical analyte, contacting the sheet material with the fluid for a time sufficient for the particles to selectively extract the analyte from the fluid, and analyzing the sheet material in a direct mode for quantitative or qualitative data relating to the radiochemical analyte. Solid phase extraction sheet materials and methods for their preparation are also disclosed.

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: The invention relates to a process for purifying radioiodides which comprisesa) passing a recovered solution of iodide over an anion exchange resin;b) washing the ion exchange resin in (a) with a solution comprising a weak base or anionic ion;c) washing the ion exchange resin in (a) with a stronger solution than used in (b); andd) recovering a solution with iodide.

Abstract: Technetium-99 is quantitatively determined in samples containing uranium using extraction chromatography to remove uranium which otherwise interferes in detecting technetium-99 in low concentrations.

Abstract: A method is presented for releasing petroleum and hydrocarbon products sorbed onto or entrained by natural fibers in an aqueous medium through the use of enzymes to degrade the natural fiber sorbents utilized for oil spill cleanup, the method provides an opportunity for achieving responsible separation of oil from oil spill sorbent materials. Natural fibers which have been utilized to adsorb petroleum and hydrocarbon products are separated from these petroleum and hydrocarbon products by reducing the natural fiber links to the point that the adsorbed or entrained oil no longer has sufficient binding surface or fiber link to remain held by the fibers, thus float to the surface of the aqueous medium. Aqueous medium enzyme compositions are provided which are suitable for degrading natural fibers inclusive of cellulose-based and protein-based fibers resulting in release of adsorbed, absorbed and/or entrained radioactive contaminants.

Abstract: Magnetic polymer resins capable of efficient removal of actinides and heavy metals from contaminated water are disclosed together with methods for making, using, and regenerating them. The resins comprise polyamine-epichlorohydrin resin beads with ferrites attached to the surfaces of the beads. Markedly improved water decontamination is demonstrated using these magnetic polymer resins of the invention in the presence of a magnetic field, as compared with water decontamination methods employing ordinary ion exchange resins or ferrites taken separately.

Abstract: A composition comprising a crosslinked, highly porous body derived from a water-soluble hydrogel polymer, said porous body being characterized in that it has an open-celled three-dimensional lattice structure, a density of less than about 1.0 g/cm.sup.3, a surface area of equal to or greater than about 300 m.sup.2 /g, a compression strength of equal to or less than about 10 percent yield at 300 psi, and an average pore diameter of less than about 500 Angstroms, wherein said hydrogel polymer is selected from the group consisting of alginates, gums, starch, dextrins, agar, gelatins, casein, collagen, polyvinyl alcohol, polyethylenimine, acrylate polymers, starch/acrylate copolymers, and mixtures and copolymers thereof; and a metal extractant.The composition may be used in removing and/or recovering metal ions from aqueous streams.

Abstract: Disclosed is a novel hydrous composite oxide of cerium (IV) and phosphorus characterized by the specified chemical composition and the unique X-ray diffractometric pattern, which is useful as an adsorbent or immobilizing agent of strontium ions in an aqueous solution such as radioactive wastes from atomic power plants. The composite oxide prepared by the precipitation reaction of a Ce (IV) salt in an aqueous solution and phosphoric acid can be imparted with an increased adsorption capacity for strontium ions when the precipitates are heat-treated under hydrothermal conditions at up to 300.degree. C. Immobilization of strontium ions adsorbed on the adsorbent can be more complete when the adsorbent bearing strontium ions is dried and subjected to a heat treatment at a temperature of 200.degree. C. or higher.