Abstract: A chemical decontamination method includes a dissolution step in which a radioactive insoluble substance containing a metal oxide, the radioactive insoluble substance being adhered to a decontamination object including carbon steel, is dissolved in a decontamination solution and a metal-ion removal step in which the decontamination solution containing the metal ion, the decontamination solution being produced in the dissolution step, is brought into contact with a cation-exchange resin in order to remove the metal ion, the dissolution step including a reductive dissolution step conducted using a decontamination solution containing formic acid, ascorbic acid and/or erythorbic acid, and a corrosion inhibitor.

Abstract: Provided are an adsorbent capable of removing radioactive water liquid including iodine compounds and/or antimony by means of a water passing treatment, and a method and an apparatus for treating radioactive waste liquid by using the adsorbent. The adsorbent includes a polymer resin and 10 parts by weight or more of a hydrous hydroxide of a rare earth element based on 100 parts by weight of the polymer resin, in which the hydrous hydroxide of the rare earth element has a water content of 1 part by weight to 30 parts by weight based on 100 parts by weight of a dry product thereof, and adsorbs iodine compounds and/or antimony.

Abstract: The cost relating to a reduction in volume and storage of a waste resin including a radioactive nuclide is reduced. In an aspect of the invention, a volume reduction processing system 1000 is provided. The volume reduction processing system 1000 includes a radioactivity meter 102 that measures the radioactivity of a processing target resin, a volume reduction processing device 110 that carries out a heating process, and an oxidation process using oxygen plasma P on the processing target resin, and a process stopping point computation unit 180 that determines a process stopping point for carrying out a volume reduction process on the processing target resin with the volume reduction processing device as far as a volume reduction target value. The volume reduction processing device 110 stops at least one process of the heating process and oxidation process on the process stopping point being reached.

Abstract: An organic synthesis of materials to achieve removal of low molecular weight ionic species, such as transition metal ions including cobalt, iron, nickel, and zinc, from aqueous solutions. The synthesis includes the steps of providing a cation exchange resin, functionalizing the cation exchange resin using a chloride intermediate to form a sulfonyl chloride resin, and reacting a multi-amine based ligand with the sulfonyl chloride resin to form a sequestration resin. The synthesis further includes the steps of cooling the sequestration resin, and washing and drying the sequestration resin.

Abstract: The present invention provides an aqueous gel composition for removing actinide ions, lanthanide ions, fission product ions, or a combination thereof from a porous surface contaminated therewith. The composition comprises a polymer mixture comprising a gel forming cross-linked polymer and a linear polymer. The linear polymer is present at a concentration that is less than the concentration of the cross-linked polymer. The polymer mixture is at least about 95% hydrated with an aqueous solution comprising about 0.1 to about 3 percent by weight (wt %) of a multi-dentate organic acid chelating agent, and about 0.02 to about 0.4 molar (M) carbonate salt, to form a gel. When applied to a porous surface contaminated with actinide ions, lanthanide ions, and/or other fission product ions, the aqueous gel absorbs contaminating ions from the surface.

Abstract: The cost relating to a reduction in volume and storage of a waste resin including a radioactive nuclide is reduced. In an aspect of the invention, a volume reduction processing system 1000 is provided. The volume reduction processing system 1000 includes a radioactivity meter 102 that measures the radioactivity of a processing target resin, a volume reduction processing device 110 that carries out a heating process, and an oxidation process using oxygen plasma P on the processing target resin, and a process stopping point computation unit 180 that determines a process stopping point for carrying out a volume reduction process on the processing target resin with the volume reduction processing device as far as a volume reduction target value. The volume reduction processing device 110 stops at least one process of the heating process and oxidation process on the process stopping point being reached.

Abstract: A method of decontaminating porous surfaces contaminated with water soluble radionuclides by contacting the contaminated porous surfaces with an ionic solution capable of solubilizing radionuclides present in the porous surfaces followed by contacting the solubilized radionuclides with a gel containing a radionuclide chelator to bind the radionuclides to the gel, and physically removing the gel from the porous surfaces. A dry mix is also disclosed of a cross-linked ionic polymer salt, a linear ionic polymer salt, a radionuclide chelator, and a gel formation controller present in the range of from 0% to about 40% by weight of the dry mix, wherein the ionic polymer salts are granular and the non cross-linked ionic polymer salt is present as a minor constituent.

Abstract: The invention provides a method for the production of a stable monolith, the method comprising the encapsulation of a waste material in the monolith by means of chemical bond formation within the monolith, and a method for the disposal and storage of waste materials, which comprises the production of a stable monolith by such method. Waste materials which are particularly suited to treatment according to the invention include various geopolymer precursors, most particularly ion exchange materials such as aluminosilicate materials, and the invention is particularly suited to the disposal and long term storage of radioactive waste materials.

Abstract: A method and apparatus for removing uranium (IV) and uranium (VI) from sands and soils. The method and device assays a volume of soil and determines a presence and position of uranium enrichment. A concentration of uranium enrichment is determined, and compared to a threshold concentration. The volume of soil is processed and transported to a coarse screen, deck screen and classified in a classifier. In the classifier, the volume of soil is separated into a washed and fines fraction, assayed and transported to a uranium recovery facility, then transported to a silicon removal process and subsequent ammonia and metals removal processes.

Abstract: This invention deals with multi-component composite materials and techniques for improved shielding of neutron and gamma radiation emitting from transuranic, high-level and low-level radioactive wastes. Selective naturally occurring mineral materials are utilized to formulate, in various proportions, multi-component composite materials. Such materials are enriched with atoms that provide a substantial cumulative absorptive capacity to absorb or shield neutron and gamma radiation of variable fluxes and energies. The use of naturally occurring minerals in synergistic combination with formulated modified cement grout matrix, polymer modified asphaltene and maltene grout matrix, and polymer modified polyurethane foam grout matrix provide the radiation shielding product. These grout matrices are used as carriers for the radiation shielding composite materials and offer desired engineering and thermal attributes for various radiation management applications.

Abstract: A surface contaminated by a radioactive isotope is cleaned by applying to it a solution that contains an ion-specific resin that is weakly bonded to an ion and a weak anion solution including a carrier, water, and an ion that frees the radioactive isotope from the contaminated surface. The radioactive isotope bonds with the ion-specific resin, replacing the ion weakly bonded to said ion-specific resin. In a preferred embodiment, the ion-specific resin is made in the counterion form of citrate, the ion that is weakly bonded to the ion-specific resin is citrate, the carrier is glycerin, the water is de-ionized or distilled, and the ion that frees the radioactive isotope from the contaminated surface is salicylate.

Abstract: A method of reducing the volume of a mixture of filter fibers and a powder-form ion-exchange resin, produces a waste product that is particularly suitable for ultimate disposal. A solvent which dissolves the filter fibers is added to the mixture and a mixture which is thus formed is first dried and then given an additional heat treatment.

Abstract: Processes and devices are disclosed for converting an aqueous waste solution, such as a radioactive waste stream, into a highly concentrated sludge having substantially little or no water. In turn, the sludge may be converted into a solid polymeric form suitable for storage. The processes utilize a carrier liquid which has a boiling point higher than that of water, and which facilitates the transfer of heat to the water to vaporize the water into steam. A subsequent separation of the dewatered solution yields the highly concentrated sludge.

Abstract: Remediation of soil, concrete and groundwater using electropotential gradient induced migration of a target ion and immobilization and/or confinement of the target ion by a host receptor matrix (HRM). In addition to immobilizing and/or confining the target ion, the HRM can comprise a buffer or an ionizable species which releases an exchange ion during application of the electropotential gradient. The exchange ion, when less mobile than a (H.sup.+) ion or hydroxyl (OH.sup.-) ion, increases the efficiency of energy usage during decontamination. The exchange ion can also perform other tasks in the vicinity of the electrodes which improve the decontamination process. The host receptor matrix can comprise a material which is water impermeable and which has a low surface energy, such as a layer of polytetrafluoroethylene film. When such a material is used, the host receptor matrix can comprise a receptacle in which there is a liquid and/or solid composition.

Abstract: Inclusion blocks of a substance chosen from ion exchange resins contaminated with radioactive elements, water which can, where appropriate, contain pollutants, solid-phase wastes in the form of blocks or pulverised preparations or liquid-phase wastes are prepared. For this purpose, the substances(s) to be included is/are embedded in a (meth)acrylic resin obtained in situ by direct polymerisation, without prior preparation of a prepolymer syrup, using a monomer system based on at least one (meth)acrylic monomer possessing a high boiling point, such as dicyclopentadienyloxyethyl methacrylate.Application to the storage of industrial pollutants, in particular substances contaminated with radioactive elements; and application of the water-inclusion blocks as prosthesis materials.