Abstract: A volume reduction process comprises combinations of a freezing eutectic, bulk, indirect crystallization process and a radwaste electrodialysis process. When employed as a liquid radioactive waste management system (LWMS) for light water reactors (LWR's), this process is designed to process liquid low-level radioactive waste (LLW) and to handle the radioactive influent in nuclear power plants (NPPs) prior to release to the environment and disposal of the radioactive material present in the waste streams.

Abstract: The improved method and apparatus are capable of efficient removal of radioactive europium from solutions of radioactive gadolinium in a simple way. A mixture of a zinc and a graphite powder is packed into a column and both a conditioning solution corresponding to a liquid electrolyte and a sample solution containing radioactive gadolinium and europium are allowed to pass through the column.

Abstract: Waste material containing hazardous or radio-active species is treated by: separating a portion of the waste material and identifying the particle size range of the severely contaminated fraction by use of a sieving apparatus (6) and a contamination detection apparatus (8); passing the waste material (15) near a contamination detection apparatus (12) to identify the waste material that is contaminated and segregate that material by a diverter (17) to provide contaminated portion (19); passing the contaminated portion (19) into a fluidized bed apparatus (16) where an aqueous leaching solution (21), effective to leach soluble, contamination species, contacts the contaminated material at an upward velocity effective to remove the particle size range that is determined to contain the severely contaminated fraction of the waste material, to provide a severely contaminated effluent slurry (24); and removing the leach solution from the slurry in a dewatering apparatus (26) to provide a solution (27) containing solub

Abstract: A process for removing metal salts from an H.sub.4 EDTA precipitate by esterification with an esterification reagent to produce an esterification mixture comprising a solid metal salt an EDTA ester and thereafter separating the solid metal salt from the esterification mixture.

Abstract: The present invention relates to a method for purification of liquids. Fur particulars, the present invention relates to a method for purifying more precisely liquids in atomic power related fields, using a mixture of a polymer in which carboxyl groups are grafted onto a polyamide or a polyester as a cation exchanger and an anion exchanger.

Abstract: Compositions comprising carbon-based supports and containing heteropolycyclic compounds such as bipyridyl, phenanthroline or derivatives thereof are used in separation of dissolved late transition metals such as Fe, Co, Ni and Cu from solutions, in particular when such solutions contain high concentrations of other dissolved metals such as Zr, Hf, La, Al and Ba. Such compositions are also used to separate late transition metals such as Pt group metals from each other.

Abstract: The invention is a gel bead comprising propylene glycol alginate and bone gelatin and is capable of removing metals such as Sr and Cs from solution without adding other adsorbents. The invention could have application to the nuclear industry's waste removal activities.

Abstract: A complex separation process and apparatus for decreasing non-radioactive salt content of waste solutions of nuclear power stations. The process significantly decreases in non-radioactive salt-content of waste solutions arising from nuclear power stations.Process is essentially based upon a suitable combination of up-to-date separating operations, such as precipitation, filtration, ultra-filtration, reverse osmosis, ion-exchange, evaporation and crystallization. Practically total amount of components carrying radioactivity (except tritium) can be effectively separated from the non-radioactive salts. Part of inactive salts (alkali nitrates) can be handled as industrial waste and the other part (boric acid) can be recycled. In the process precipitation, ion-exchange, reverse osmosis and crystallization are operations completing or replacing each other. Reverse osmosis is used not only for separating water and soluble, but for the separation of solved components.

Abstract: The invention is a gel bead comprising propylene glycol alginate and bone gelatin and is capable of removing metals such as Sr and Cs from solution without adding other adsorbents. The invention could have application to the nuclear industry's waste removal activities.

Abstract: An ion exchange material comprises an oxide of a first element selected from elements of Groups IVa, IVb, Va, Vb, VIa, VIb, VIIa, or lanthanide or actinide series of the Periodic Table, in combination with an oxide of at least one different element selected from elements of the afore-mentioned groups of the Periodic Table so as to form a composite material. For example, a composite ion exchange material may comprise silicon dioxide and manganese dioxide. By selecting the appropriate oxides a composite ion exchange material can be prepared which has greater mechanical and/or chemical stability than an individual oxide of the composite material.

Abstract: A method for extracting metal ions by contacting an aqueous solution containing the metal ions with an acidic phosphoric acid ester, characterized in that as the acidic phosphoric acid ester, an acidic phosphoric acid ester of the formula: ##STR1## wherein R.sup.1 is an alkylphenyl group having from 7 to 18 carbon atoms and R.sup.2 is an alkyl group having from 1 to 18 carbon atoms, is used.

Abstract: The separation of uranium, iron and scandium is achieved by the following process wherein a material containing these values is dissolved in mineral acid to form an aqueous solution, thereafter, an iminodiacetic acid cationic ion exchange resin is used to retain a major portion of the scandium and uranium. A raffinate containing the iron is formed. The ion exchange resin having said scandium and uranium retained thereon is rinsed with a dilute acid to remove residual metals other than scandium and uranium. The resin is eluted with an aqueous solution of an organic chelating acid to remove a major portion of the scandium from said resin and to form an aqueous solution containing scandium. The resin is then eluted with an aqueous solution of a mineral acid to remove a major portion of the uranium from the resin to form an aqueous solution containing the uranium. The scandium and uranium are recovered as solids.

Abstract: A filter for a respirator for removal of tritiated water having a housing with fluid inlet and output ports. A filter chamber is interposed between and in communication with the inlet and outlet for containing the tritium filter medium. A tritium filter media is selected from a particulate activated carbon or a particulate silica gel in which the media has a moisture content of from about 25% to 40% by weight of the media and a particulate distribution size range of from 6.times.20 to 12.times.30.

Abstract: Ion exchange performed by contacting a solution containing ions to be absorbed with a hydrous oxide of uranium in a suitable form. The hydrous oxide may be uranium dioxide or uranium hydroxide, and may be prepared by reducing a uranium species, precipitating the reduced species, and drying the precipitate to give the required hydrous oxide.

Abstract: The present invention relates to a process for removing radioactive ruthenium from an aqueous solution, comprising oxidizing the ruthenium in the aqueous solution of ruthenium tetroxide, extracting the resulting ruthenium tetroxide with a halogen-free aliphatic or alicyclic hydrocarbon solvent, allowing the ruthenium tetroxide to be reduced in the solvent, and separating the precipitated solid ruthenium dioxide.

Abstract: Iodine and organic iodine compounds which may be radioactive and which may be found in waste gases or vapors from nuclear reactors can be removed from such gases or vapors by passing the iodine or organic iodine compound-containing gases or vapors through a layer of binder-free silver-exchanged molecular sieve granulates of the faujasite type.

Abstract: A process for pretreatment of chromium-rich oxide surfaces of nuclear reactor cooling system components involves application of a dilute acidic reagent comprising potassium permanganate and chromic acid, at elevated temperatures.

Abstract: The present invention comprises a process for separating rare earth ions or actinide ions or mixtures thereof in solution by passing the solution through an ion exchange material to separate the rare earths or actinides or mixtures thereof. The ion exchange material has a surface area of about 5-1500 m.sup.2 /g. The ion exchange material is impregnated with a liquid containing alkali metal cations, Group Ib metal cations, ammonium cations, organic amines or mixtures thereof, at a pH range above about 9. A plurality of fractions of the solution is collected as the solution passes through the ion exchange material, preferably in a column. This process is particularly preferred for separating rare earth ions and especially lanthanum and neodymium. It is particularly preferred to purify lanthanum to contain less than 0.1 ppm, preferably less than 0.01 ppm, of neodymium.

Abstract: Process for the purification of reprocessing uranium from which have previously been separated the fission products generated in a nuclear reactor and consisting of eliminating the U232 daughter products appearing during storage, by passing said uranium in its hexafluoride form through a chemically inert porous material.

Abstract: A process and an apparatus for cleaning nuclear reactor cooling water with cation exchange resin whose ion-exchanging groups have a bonding energy of not more than 300 KJ/mole are disclosed, whereby the radiation exposure of operators in an atomic power plant can be considerably reduced, and the waste ion exchange resin can be readily disposed.

Abstract: Ruthenium in aqueous solution in a first, oxidizable oxidation state (e.g. as RuNO(NO.sub.3).sub.3) is converted to an insoluble form in a second, different oxidation state (e.g. as RuO.sub.2.nH.sub.2 O) by establishing an electrochemical cell wherein the solution is the electrolyte and electrochemically oxidizing and reducing the ruthenium in the cell. The insoluble form may be filtered from the liquid. The ruthenium treatment may be a stage in the removal of radioactive species from liquids such is in the treatment of medium and low level activity liquid waste streams, wherein actinides are precipitated and filtered off either before or after ruthenium treatment. Subsequently, residual activity may be removed from the stream by either or both of (a) absorption, followed by filtration and electro-osmotic dewatering and (b) electrochemical ion exchange. Filtration fluxes may be maintained by direct electrochemical membrane cleaning.

Abstract: A method of oxidatively decomposing a radioactive ion-exchange resin is described, the method comprising oxidatively decomposing a radioactive ion-exchange resin containing an anion-exchange resin with hydrogen peroxide used as an oxidizing agent in the presence of iron and copper ions used as catalysts, wherein the weight ratio of hydrogen peroxide to the ion-exchange resin, that is the ratio of the net weight of hydrogen peroxide to the dry weight of the ion-exchange resin containing an anion-exchange resin, is held to be no higher than 17 and the pH of the reaction system is adjusted to be within the range of 0.5 to 6, or citric acid ions are preliminarily adsorbed on the radioactive ion-exchange resin before it is subjected to decomposition treatment or citric acid ions coexist with the radioactive ion-exchange resin in the oxidatively decomposing system, and an apparatus used for conducting the method is also described.

Abstract: Compositions comprising carbon-based supports and containing heteropolycyclic compounds such as bipyridyl, phenanthroline or derivatives thereof are used in separation of dissolved late transition metals such as Fe, Co, Ni and Cu from solutions, in particular when such solutions contain high concentrations of other dissolved metals such as Zr, Hf, La, Al and Ba. Such compositions are also used to separate late transition metals such as Pt group metals from each other.

Abstract: A process for the extraction of cations from an aqueous effluent. An effective quantity of at least one polymer or copolymer, which is physically or chemically crosslinked, is introduced into the aqueous effluent. The polymer or copolymer is based on one or more units selected from salified acrylic acid, quarternized acrylic acid, and a copolymer comprising from 40 to 60 mole % of acrylic acid and from 60 to 40 mole % of at least one dialkylaminoalkyl acrylate in which each alkyl group contains from 1 to 4 carbon atoms. This process is used to treat aqueous effluents.

Abstract: There is provided a generator for short-lived radionuclides. The generator comprises a support, an ion-exchange agent and a parent radionuclide in a steady-state equilibrium with a daughter nuclide, which daughter nuclide can be selectively eluted from said column. A suitable parent radionuclide is .sup.191 OS in equilibrium with .sup.191m Ir. There is also provided a specific Os(VI) complex which has certain advantages.

Abstract: A method for extracting metal ions by contacting an aqueous solution containing the metal ions with an acidic phosphoric acid ester, characterized in that as the acidic phosphoric acid ester, an acidic phosphoric acid ester of the formula: ##STR1## wherein R.sup.1 is an alkylphenyl group having from 7 to 18 carbon atoms and R.sup.2 is an alkyl group having from 1 to 18 carbon atoms, is used.

Abstract: A new process for treating waste liquids of acid decontamination agent is disclosed which comprises the steps of neutralizing a waste liquid of acid decontamination agents with an alkali, filtering out suspended matter from the neutralized waste liquid using a filter, removing inhibitors from the filtered waste liquid by adsorption with activated charcoal, removing radioactive ions from the waste liquid treated by activated charcoal with a chelate resin, concentrating the chelate resin-treated waste liquid by evaporation, and bituminizing the concentrate obtained in the preceding step.

Abstract: A method 20 for decontaminating specially selected plastic materials comprised of polymers and copolymers of unsaturated organic acids and other specially selected plastic materials, which have become radioactively contaminated, includes dissolving such plastic materials in an aqueous solvent 34 and treating the resulting solution selectively via filtration 36, ion-exchange absorption 40, and precipitation 44 processes to remove particulate and dissolved radioactive contaminants. The treated aqueous stream may be discharged to a sewage stream and the separated plastic materials can be disposed of in a sanitary landfill or recycled into other plastic products.

Abstract: A method 20 for decontaminating plastic products and materials which have become radioactively contaminated. The treatment method 20 involves dissolving such plastics in a dissolution tank 28 in an organic solvent and treating the resulting solution by a solvent extraction technique in column 36 to remove particulate and dissolved radioactive contaminants from the plastic. The contaminants can be buried in a low level radioactive waste site and the separated plastic material can be disposed of in a sanitary landfill or recycled into other plastic products.

Abstract: A process for the separation of radioisotopes and stable isotopes and other deleterious materials from radioactive waste and other liquids, wherein the waste stream is passed through a filter/demineralizer septum screen pre-coated with a mixture of finely-divided zeolitic material and finely-divided ion-exchange resin material.

Abstract: A method and apparatus for a regenerating dynamic adsorber system which removes a contaminant from fluid. The system includes at least one adsorption bed having a contaminant removal capacity that is based substantially on the flow of the contaminated fluid through the bed. The system alternately cleanses the contaminated fluid by feeding the contaminated fluid from a first volume to the bed and issuing cleansed fluid to a second volume, and regenerates the bed by providing clean fluid from a third volume and issuing the fluid back to the third volume.

Abstract: The insitu method of detoxifying a hazardous waste impoundment to a desired degree at a first station thereon without contaminating the ambient atmosphere is carried out by an apparatus (U) that includes a power operated vehicle (V) that movably supports a frame (W) that has a confined space defining shroud (X) on the lower end thereof that is in sealing contact with the impoundment during the carrying out of the method. A power driven cutter (Z) when moved downwardly below the shroud (X) forms a vertical zone A of particled hazardous waste. Pressurized steam from a boiler (B) is discharged into zone A. Volatile toxic organic compounds in zone (A) flow upwardly into shroud (X). A blower (C) withdraws air, steam, toxic vapors and toxic gases from shroud (X) as a toxic stream and at a sufficiently rapid rate as to maintain a negative pressure within the shroud, with the stream after being freed of toxic components by a unit (P) being returned to zone A.

Abstract: A process for removing organic compounds from a nuclear waste slurry comprising reacting a mixture of radioactive waste precipitate slurry and an acid in the presence of a catalytically effective amount of a copper (II) catalyst whereby the organic compounds in the precipitate slurry are hydrolyzed to form volatile organic compounds which are separated from the reacting mixture. The resulting waste slurry, containing less than 10 percent of the orginal organic compounds, is subsequently blended with high level radioactive sludge and transferred to a virtrification facility for processing into borosilicate glass for long-term storage.

Abstract: The invention relates to a process for improving the effectiveness of the removal of zirconium from an aqueous, zirconium-containing nuclear fuel and/or fertile material solution in nitric acid in a liquid-liquid extraction process.Accordingly, the object of the invention is to improve the removal of zirconium from the reprocessing solutions and, at the same time, to simplify the course of the process. The invention seeks to improve decontamination of the uranium product and the plutonium product while, at the same time, reducing the outlay involved.According to the invention, this object is achieved in that, in a process step carried out before the first extraction of the nuclear fuels and/or fertile materials, the zirconium is converted from the dissolved state into a filterable or centrifugable solid phase by the use of an adsorbent from the group of inorganic ion exchangers and is removed from the aqueous solution together with the adsorbent.

Abstract: Silica gels modified with amino groups or magnesium silicates are suitable carrier materials for technetium-99m generators since they retain copper(II) ions well and thus produce a copper-free eluate.

Abstract: The present invention relates to a new technique and device for mass transport operation and physical separation, being substantially quantitative and involving selective barriers. According to the new technique, the mass transport through the selective barrier and physical separation are carried out in the same device. The device consists of a mixing-reservoir into which is fitted snugly a mixer-separator, having a channel in the vertical axis of the mixer-separator, the mixer-separator being provided with means for accumulating a gas pocket to decrease the pressure exerted on the barrier. The completely solid-free liquid passing through the selective barrier is removed by pushing in the mixer-separator, said liquid being accumulated in a collecting container. Typical examples of such selective barriers are: membrane, bed of adsorbent material, paper, plastic, glass and metal filters or any other porous material, hollow fibers etc.

Abstract: A portable, submersible water purification system for use in a pool of water containing radioactive contamination includes a prefilter for filtering particulates from the water. A resin bed is then provided for removal of remaining dissolved, particulate, organic, and colloidal impurities from the prefiltered water. A sterilizer then sterilizes the water. The prefilter and resin bed are suitably contained and are submerged in the pool. The sterilizer is water tight and located at the surface of the pool. The water is circulated from the pool through the prefilter, resin bed, and sterilizer by suitable pump or the like. In the preferred embodiment, the resin bed is contained within a tank which stands on the bottom of the pool and to which a base mounting the prefilter and pump is attached. An inlet for the pump is provided adjacent the bottom of the pool, while the sterilizer and outlet for the system is located adjacent the top of the pool.

Abstract: The invention relates to a process for continuous or almost continuous separation of cesium ions from aqueous solutions having high concentrations of sodium and/or potassium ions by ion exchange with ammonium molybdophosphate (AMP).A quantitative cesium separation from aqueous solutions which are high in salts, especially from highly radioactive solutions which are strongly nitric and contain nitrate, is achieved, without having to consider bleeding of the AMP and/or undesirable local overheating in the exchanger.

Abstract: A process for treating a waste water containing uranium and fluorine comprises a neutralizing precipitation step wherein slaked lime is added to the waste water containing uranium and fluorine and precipitate thus formed in separated and removed, and an adsorption step wherein supernatant from the neutralizing precipitation step is contacted with a chelating resin which can selectively adsorb fluorine ions and another chelating resin which can selectively adsorb uranyl ions to thereby adsorb and remove the fluorine and uranyl ions remaining in the supernatant. Eluates of the ions adsorbed by the chelating resins and waste liquors for washing and regeneration of these resins are returned to the neutralizing precipitation step. Prior to the neutralizing precipitation step, a decarbonation step may be provided for decomposing carbonate ions, if they are contained in the waste water to be treated.

Abstract: Cesium can be selectively recovered from a nuclear waste solution containing cesium together with other metal ions by contact with a modified phlogopite which is a hydrated, sodium phlogopite mica. Once the cesium has entered the modified phlogopite it is fixed and can be safely stored for long periods of time.

Abstract: A soluble salt (sodium sulfate or sodium borate (Na.sub.2 SO.sub.4 or Na.sub.2 B.sub.4 O.sub.7) contained as the main component in a concentrated radioactive waste liquid generated in the BWR power plant or the PWR power plant is insolubilized and precipitated, sodium hydroxide (NaOH formed in the insolubilization is separated from the precipitate and the radioactive waste liquid slurry containing the precipitate is solidified with a hydraulic solidifying material. Since the separated caustic soda (NaOH) is free of radioactive substances, it can be easily utilized again, and since the radioactive substances are stably fixed in the solidified body, leakage of radioactivity from the solidified body can be greatly reduced.

Abstract: A method of treating a heavy metal and/or a radioactive metal-containing natural water or liquid such as a radioactive metal-containing wastewater stream, a potable water supply containing naturally-occuring radioactive elements, an oil containing one or more radioactive metals, or other nuclear metal-bearing liquid by contacting the radioactive heavy metal-containing liquid with a water-insoluble carboxylated cellulose-transition metal oxide mixture to separate the heavy metals from the liquid. The heavy metal and radioactive heavy metals precipitate from the liquid onto the cellulose material to form a radioactive metal-laden solid material. The radioactive metal-laden solid then is air-dried, calcined and/or admixed with a leach-resistant matrix, such as grout or asphalt, for suitable disposal.

Abstract: The present invention relates to a method and an apparatus for producing a waste package of radioactive waste containing particles of radioactive waste material of low modulus of elasticity, particles of radioactive waste material of high modulus of elasticity, and a solidifying agent in which the particles of radioactive waste material of low modulus of elasticity and the particles of radioactive waste material of high modulus of elasticity are fixed in an almost uniformly dispersed state. According to this invention, the radioactive waste generated from nuclear power plants can be greatly reduced in volume and also a waste package of radioactive waste with high strength and excellent water resistance can be obtained.

Abstract: A process for the stripping of cesium ions from an aqueous solution in which a precipitation agent is added to the aqueous solution and the resulting precipitate, containing the CS.sup.+ ions is stripped from the solution. Sodium or lithium tetraphenylborates, carrying electron-attracting substituents on the phenyl rings are employed as precipitation agent.

Abstract: A layer of small-sized particles of an organic ion exchange resin is applied to a support matrix, permeable to liquid, of a filter element (7) which is arranged in a chamber (5) in an ion-exchange filter (1) for filtering of liquids containing radioactive constituents. The filter and a mixer (11), consisting of a tube with a number of stationary mixing elements arranged one after the other in the longitudinal direction of the tube, are arranged in a circulation system (10) for water. The mixing elements successively divide up a material flow, supplied at the inlet end of the mixer, into a number of sub-flows containing different parts of the original material flow and the sub-flows are reunited, before they reach the outlet end of the tube. Suspended ion-exchange resin (13a, 16a) is supplied to the inlet end (11a) of the mixer for the circulating water while the water is being circulated in the circulation system.

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: Disclosed is a method of making an ion exchange material. A ceramic material is ion implanted with sulfur, carbon, phosphorus, or nitrogen, which is oxidized to sulfate, carboxylate or carbonate, phosphate, or nitrate, respectively, or the nitrogen is reduced to amine amide. Alternatively, a mixture of ceramic powder and a binder containing sulfur, carbon, phosphorus, or nitrogen is heated in a nonoxidizing atmosphere to a temperature up to 1000.degree. C. The sulfur is then oxidized to sulfate, the carbon to carboxylate or carbonate, phosphorus to phosphate, and nitrogen to nitrate, or the nitrogen is reduced to amine or amide. Also disclosed is an ion exchange material made by these methods and a method of treating acidic aqueous solutions containing dissolved radioactive materials by passing them through an ion exchange column containing the ion exchange material.

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: The process of the present invention comprises adding an alkaline earth metal hydroxide such as barium hydroxide to a radioactive liquid waste containing sodium sulfate as the main component to convert the latter into an insoluble alkaline earth metal salt such as barium sulfate, adding silicic acid to by-product sodium hydroxide to prepare water glass and solidifying the radioactive insoluble alkaline earth metal salt with the water glass. According to this process, exudation of radioactive substances from the solid can be prevented and the solid having a high durability can be obtained at a low cost.

Abstract: A process for the removal of iodine from aqueous solutions, particularly the trapping of radioactive iodine to mitigate damage resulting from accidents or spills associated with nuclear reactors, by exposing the solution to well dispersed silver carbonate which reacts with the iodine and iodides, thereby gettering iodine and iodine compounds from solution. The iodine is not only removed from solution but also from the contiguous vapor.