Abstract: The manufacturing method includes a granulation step. The granulation step is a step of forming a plurality of granules by performing extrusion granulation on a granulation material using a granulation machine. The granulation machine includes a die. A plurality of through holes that allow the granulation material to pass therethrough are formed in the die. The plurality of through holes include first through holes having a first diameter, and second through holes having a second diameter that is smaller than the first diameter.

Abstract: The present invention relates to a method and covalent bonding process for fixing tritiated water into a polystyrene based product for the permanent elimination of tritiated water from the environment.

Abstract: A process for encapsulating a radioactive object to render the object suitable for shipment and/or storage, and including the steps of preparing a plastic material, causing the plastic material to react with a foaming agent, generating a foaming plastic, encapsulating the radioactive object in the foaming plastic, and allowing the foaming plastic to solidify around the radioactive object to form an impervious coating.

Abstract: A process for encapsulating a radioactive object to render the object suitable for shipment and/or storage, and including the steps of preparing a plastic material, causing the plastic material to react with a foaming agent, generating a foaming plastic, encapsulating the radioactive object in the foaming plastic, and allowing the foaming plastic to solidify around the radioactive object to form an impervious coating.

Abstract: The present invention intends to provide a method for removing radioactive cesium, or radioactive iodine and radioactive cesium that is simple and low-cost, further does not require an energy source such as electricity, moreover can take in and stably immobilize the removed radioactive substances within a solid, and can reduce the volume of radioactive waste as necessary, and to provide a hydrophilic resin composition using for the method for removing radioactive cesium, or radioactive iodine and radioactive cesium, and the object of the present invention is achieved by using a hydrophilic resin composition containing: at least one hydrophilic resin selected from the group consisting of a hydrophilic polyurethane resin, a hydrophilic polyurea resin, and a hydrophilic polyurethane-polyurea resin each having at least a hydrophilic segment; and a zeolite dispersed therein in a ratio of at least 1 to 200 mass parts relative to 100 mass parts of the hydrophilic resin.

Abstract: A process for encapsulating a radioactive object to render the object suitable for shipment and/or storage, and including the steps of preparing a plastic material, causing the plastic material to react with a foaming agent, generating a foaming plastic, encapsulating the radioactive object in the foaming plastic, and allowing the foaming plastic to solidify around the radioactive object to form an impervious coating.

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: A selective polymer-wrapping process is disclosed which is capable of exclusively wrapping radioactive particles from solid waste streams at room temperature. Accordingly, separation of wrapped radioactive particles from unwrapped non-radioactive particles is facilitated. The method includes exposing radioactive particles or material, alone or in combination with other materials, to a precursor monomer solution that is capable of polymerizing due to the inherent radiation of the radioactive material, whereby the radioactive material is partially or totally encapsulated in the resultant polymer.

Abstract: This invention is directed to methods for treating radioactive-containing waste materials. Even more specifically, this invention relates to the prevention of radon emissions by encapsulating the radon in radon-generating waste matter using a chemical additive. Alternatively, the amount of radon escaping into the environment may be minimized by adjusting the shape of the carrier which stores the radon generating waste matter. Additionally, the first two embodiments may be combined to ensure that the radon does not escape into the environment. Finally, polymer sealants may be used as an additional barrier layer.

Abstract: This invention is directed to methods for treating radioactive-containing waste materials. More specifically, the present invention relates to the prevention of radon emissions. Even more specifically, this invention relates to the prevention of radon emissions by encapsulating the radon in radon-generating waste matter using a chemical additive. Alternatively, the amount of radon escaping into the environment may be minimized by adjusting the shape of the carrier which stores the radon-generating waste matter. Additionally, the first two embodiments may be combined to ensure that the radon does not escape into the environment. Finally, polymer sealants may be used as an additional barrier layer.

Abstract: The present invention is directed to a material-radioactive isotope combination, comprising a container made from a material and a radioactive isotope solution. The container is useful for the storage, shipment, or storage and shipment of the radioactive isotope. Preferably the material is characterized by having a nearly full compliment of double carbon bonds so that little, or no hydrogen is produced by the material in the presence of the radioactive isotope. Furthermore, the preferred material exhibits greater mechanical strength than that of glass, resistance to a temperature range of from about -40.degree. to about 160.degree. C., chemical inertness; and radiation resistance. An example of such materials includes PSF (polysulfone) and PETG (polyethylene terephalate G copolymer) and the radioactive isotope, of the material-radioactive isotope combination are selected from, the group consisting of Mo-99, I-131, I-125. W-188 and Cr-51.

Abstract: The present invention provides a process of encapsulating depleted uranium by forming a homogenous mixture of depleted uranium and molten virgin or recycled thermoplastic polymer into desired shapes. Separate streams of depleted uranium and virgin or recycled thermoplastic polymer are simultaneously subjected to heating and mixing conditions. The heating and mixing conditions are provided by a thermokinetic mixer, continuous mixer or an extruder and preferably by a thermokinetic mixer or continuous mixer followed by an extruder. The resulting DUPoly shapes can be molded into radiation shielding material or can be used as counter weights for use in airplanes, helicopters, ships, missiles, armor or projectiles.

Abstract: A method of encapsulating mixed waste in which a thermoplastic polymer having a melting temperature less than about 150.degree. C. and sulfur and mixed waste are mixed at an elevated temperature not greater than about 200.degree. C. and mixed for a time sufficient to intimately mix the constituents, and then cooled to a solid. The resulting solid is also disclosed.

Abstract: The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining substantially simultaneously dry waste powder, a non-biodegradable thermoplastic polymer and an anhydrous additive in an extruder to form a homogenous molten matrix. The molten matrix may be directed in a "clean" polyethylene liner, allowed to cool, thus forming a monolithic waste form which provides a multibarrier to the dispersion of wastes into the environment.

Abstract: The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining substantially simultaneously dry waste powder, a non-biodegradable thermoplastic polymer and an anhydrous additive in an extruder to form a homogenous molten matrix. The molten matrix may be directed in a "clean" polyethylene liner, allowed to cool, thus forming a monolithic waste form which provides a multibarrier to the dispersion of wastes into the environment.

Abstract: The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining substantially simultaneously dry waste powder, a non-biodegradable thermoplastic polymer and an anhydrous additive in an extruder to form a homogenous molten matrix. The molten matrix may be directed in a "clean" polyethylene liner, allowed to cool, thus forming a monolithic waste form which provides a multibarrier to the dispersion of wastes into the environment.

Abstract: A method for disposing of waste material employs an agglomerate formed by molding an admixture of waste material and thermosetting binder. The use of a thermoplastic resin sheet in conjunction with the agglomeration mold promotes the safety of the molding process. Dust and mold leakage is abated and it subsequently yields a resin coated agglomerate that is safe for handling. The performance of the agglomerate is enhanced by formation of a coating of resin chemically bonded onto its surface. The performance of the agglomerate may be further enhanced by the formation of a seam-free thermoplastic resin jacket over the resin coated agglomerate.

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: A method of containing hazardous and toxic wastes includes the steps of irporating the dried waste, in a salt form, in melted polymer, such as asphalt, and forming the waste salt and asphalt blend into aggregate pellets. The pellets are coated with a powdered coating material that is compatible with a portland cement-based mortar or other cementitious material which is used. The coated particles are mixed with mortar to form a polymer-aggregate concrete and cast into wasteforms for storage or burial. If it is desirable to produce a waste form with a continuous layer of mortar on the exterior of the concrete monolith the mold can be placed on a turntable and spun, or otherwise exposed to a centrifugal force to force the mortar to the outside of the mold. Centrifugal separation is possible because the polymer-waste mixture typically has a specific gravity near 1.5 while that of the cementitious mixture is typically greater than 2.0.

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.