Abstract: There is provide herein a compound of Formula (1): wherein R1, R2, R3, R4, and R5 are each independently H or an organic group.

Abstract: A glass manufacturing apparatus includes a dissolving vessel configured to dissolve a glass raw material to produce a molten glass, a forming vessel configured to form the molten glass into a predetermined shape, and glass supply tubes configured to convey the molten glass from the dissolving vessel to the forming vessel. The glass supply tubes each include a tube body, a flange portion, which is arranged in an outer circumferential portion of the tube body and has first and second parts, an electrode portion arranged in the first part, and a temperature difference setting portion configured to cause a temperature difference between the first and second parts. The temperature difference setting portion sets a temperature of the first part to be higher than that of the second part.

Abstract: Processes, systems, and methods for selectively regenerating an ion exchange resin generally comprises washing the ion exchange resin with an elution agent that encourages only selected contaminants, and especially selected radioactive isotopes, to disengage or decouple from the resin and enter solution in the elution agent, which thereafter is identified as the elution agent solution. The elution agent solution is then passed through a column of isotope-specific media (ISM). When the selected radioactive isotopes within the elution agent solution come into contact with the constituent media isotopes of the ISM, the selected radioactive isotopes are retained on the reactive surface areas of the ISM or within the interstitial spaces of the porous structures of the constituent media isotopes of the ISM. In some embodiments, the constituent media isotopes of the ISM are embedded, impregnated, or coated with the specific radioactive isotope that the particular ISM are adapted to separate.

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 clay mineral dispersed therein in a ratio of at least 1 to 180 mass parts relative to 100 mass parts of the hydrophilic resin.

Abstract: Disclosed is a method for treating a radioactive organic waste, the radioactive organic waste including a cation exchange resin adsorbing radionuclide ions, the method including the step of bringing the radioactive organic waste into contact with an organic acid salt aqueous solution containing an organic acid salt and whereby desorbing the radionuclide ions from the cation exchange resin, in which the organic acid salt contained in the organic acid salt aqueous solution includes a cation that is more readily adsorbable by the cation exchange resin than hydrogen ion is. This enables reduction in concentration of a radioactive substance in the radioactive organic waste and reduction in amount of a high-dose radioactive waste.

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 method for removing radioactive cesium and/or iodine from a radioactive substance in liquid and/or a solid matter using a hydrophilic resin composition comprising a hydrophilic resin and a metal ferrocyanide compound, wherein the hydrophilic resin includes 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 metal ferrocyanide compound is dispersed in the hydrophilic resin composition in a ratio of at least 1 to 200 mass parts relative to 100 mass parts of the hydrophilic resin.

Abstract: The present invention relates to a radioactive cesium adsorbent, a method for producing the same, and a method for decontaminating the environment from radioactive cesium with the adsorbent. The radioactive cesium adsorbent of the present invention includes a hydrophilic fiber substrate supporting a Prussian blue analogue, in particular, Prussian blue, and the Prussian blue analogue is immobilized in the inside of the fibers.

Abstract: The present invention relates to a method for treating various waste petroleum into eco-friendly solid so that leaching of oil would not occur. The method of the present invention can treat radioactive waste petroleum as well as various waste petroleum, thereby stabilizing waste petroleum chemically and physically, wherein the method comprises mixing waste petroleum with a sulfuric acid and a nitric acid; adding sodium hydroxide, thereby carrying out a polymerization reaction to produce solid particles; colloidizing a mixture obtained by uniformly stirring the solid particles; adding a diisocyanate compound in reactor, thereby carrying out a subsequent polymerization reaction to obtain a new compound in the form of powder; discharging a generated gas into the atmosphere; and filling the powder into a resin as a filling material and compression molding and reclaiming the filled powder.

Abstract: By fibrillated cellulose fibrillated in fiber form and humidified as a water permeable polymeric substance of botanical origin and a radioactive-substance-absorbent obtained by mixing with zeolite as a granulated inorganic porous crystal, radioactive substances released and spilled in a accident etc. in a nuclear facility etc. may be efficiently and easily collected and removed at a low cost.

Abstract: A nuclear chemistry laboratory adopts In-site Cutting Technique to remove the large-scale glove box contaminated by transuranium compounds. During removal operation, to prevent further spreading of contamination, it is necessary to build an alpha airtight quarantine tent around the glove box that is ready to be cut. Each section of the quarantine tent maintains a stable airflow and sufficient air exchange to meet negative pressure requirements and effectively prevent leak of ? contamination. It is necessary to install a negative pressure ventilation system to assure the operation of the quarantine tent that has a pressure gradient and allows airflow from low contamination area to high contamination area to effectively prevent spreading of ? contamination and also increase the safety for the transuranium contaminated glove box that is not in service.

Abstract: A polymeric hypernucleophilic catalyst is effective for hydrolytic destruction of chemical threat agents under mild conditions, e.g., near neutral pH and at ambient temperatures. The polymeric hypernucleophilic catalysts are particularly useful to affect rapid destruction of chemical threat agents on sensitive surfaces such as paint, metal, rubber, plastic, fabric, wood, and skin. Catalyst formulations such as creams, lotions, sprays, foams, powders, or gels, and articles such as filters, wipes, membranes, yarns, fabrics, and articles of clothing, may be used for detoxification of or prophylactic protection against chemical threat agents.

Abstract: The present invention relates to a method of capturing radioactive species in an aqueous solution and removing the radioactive species for disposal. The method includes the steps of providing a macroporous bead form sequestration resin, subjecting the bead form sequestration resin to radioactive species contained in the aqueous solution to allow the bead form sequestration resin to capture the radioactive species; and disposing the radioactive species in a radioactive storage facility.

Abstract: The invention relates to a process for separating, in an aqueous medium, at least one actinide element from one or more lanthanide elements by using at least one molecule which sequesters the said actinide element to be separated and membrane filtration, the said process successively comprising: a) a step of bringing at least one molecule which sequesters the said actinide element in contact with the aqueous medium, the said molecule not being retained in the non-complexed state by the said membrane and being capable of forming a complex with the actinide element to be separated, comprising the said element and at least two of the said sequestering molecules, which complex is capable of being retained by the membrane; b) a step of passing the aqueous medium over the membrane in order to form a permeate on one side, comprising an aqueous effluent depleted of the said actinide element, and a retentate comprising the said complex.

Abstract: A protected organoboronic acid includes a boron having an sp3 hybridization, a conformationally rigid protecting group bonded to the boron, and an organic group bonded to the boron through a boron-carbon bond. A method of performing a chemical reaction includes contacting a protected organoboronic acid with a reagent, the protected organoboronic acid including a boron having an sp3 hybridization, a conformationally rigid protecting group bonded to the boron, and an organic group bonded to the boron through a boron-carbon bond. The organic group is chemically transformed, and the boron is not chemically transformed.

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 present invention relates to a method for treating various waste petroleum into eco-friendly solid that leaching of oil would not occur. The method of the present invention can treat radioactive waste petroleum used in a nuclear power station as well as various waste petroleum, thereby stabilizing waste petroleum chemically and physically, wherein the method comprises mixing waste petroleum with a concentrated sulfuric acid and a concentrated nitric acid; adding sodium hydroxide, thereby carrying out a second polymerization reaction to produce solid particles; colloidizing a mixture obtained by uniformly stirring the solid particles; adding a diisocyanate compound in reactor, thereby carrying out a third polymerization reaction to obtain a new compound in the form of powder; discharging a generated gas into the atmosphere; and filling the compound into a resin as a filling material and compression molding and reclaiming the filled compound.

Abstract: Techniques and compositions are provided for shielding radioactive energy. The composition includes a hydrocarbon component and a radiation shielding and absorbing material or additive. The composition may be applied to substrates or to radioactive materials. Moreover, the composition may be mixed with raw materials of products.

Abstract: A decontamination gel is obtained to be spayed on a contaminated material. Places of contaminations of Co, Cs and Sr are shown by the gel. Then the gel is dried up in the air to form a film. Thus, the contaminations are cleaned by removing the film.

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: Techniques and compositions are provided for shielding radioactive energy. The composition includes a hydrocarbon component and a radiation shielding and absorbing material or additive. The composition may be applied to substrates or to radioactive materials. Moreover, the composition may be mixed with raw materials of products.

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: A Method and Device for solidification of waste liquids and fluids is disclosed. The invention is particularly well suited to processing radioactive waste fluids; and employs a metered polymer supply assembly and metered waste supply assembly, which have a prescribed positional orientation in relation to themselves and a container. These assemblies operate in relation to each other to meter, mix and position a solidification agent or polymer with a waste fluid so that a dirt-like polymerized waste product is produced and positioned in the container for safe shipment or storage. The waste supply assembly in a preferred embodiment is provided with a novel waste trough. Prescribed mathematical relationships for determining the trough length, and the cross-sectional dimensional relationship of the polymer chute of the invention in relation to the cross-sectional dimensional magnitude of the waste trough is set forth.

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: This invention relates to a method of strong/tight packaging an object in order to prepare it for shipping. Initially, a substrate is applied to an object to create a smooth surface adapted to receive a sprayable plastic thereon. Then, the sprayable plastic is sprayed onto the substrate and the object to encapsulate the object.

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: A low viscosity resin is delivered into a spent HEPA filter or other waste. The resin is introduced into the filter or other waste using a vacuum to assist in the mass transfer of the resin through the filter media or other waste.

Abstract: A method for remediating non-homogeneous radioactive waste to significantly reduce the waste mass/volume and to convert such waste to products that meet federal regulatory compliance standards is disclosed. High level waste (HLW) stored in underground tanks is typically a multi component mixture. After removal of the waste from the tanks or other storage areas the waste is isolated in a thermal desorption-type reaction vessel where the waste is pyrolized at pre-determined and carefully controlled temperatures, pressures, and atmospheres. This process eliminates organics, volatile metals, moisture and other low boiling temperature/high vapor pressure components and converts non-volatile waste to more stable metal oxides. Off-gas treatment systems scrub, treat and dispose of all off-gas components. A thermal desorption-type apparatus especially well suited for performing the method of the present invention is also disclosed.

Abstract: A gel composition containing oxidizing agents and thickening or gelling agents is used to detoxify chemical and biological agents by application directly to a contaminated area. The gelling agent is a colloidal material, such as silica, alumina, or alumino-silicate clays, which forms a viscous gel that does not flow when applied to tilted or contoured surfaces. Aqueous or organic solutions of oxidizing agents can be readily gelled with less than about 30% colloidal material. Gel preparation is simple and suitable for field implementation, as the gels can be prepared at the site of decontamination and applied quickly and uniformly over an area by a sprayer. After decontamination, the residue can be washed away or vacuumed up for disposal.

Abstract: A process for disposing of solvent-containing liquids so that they do not contaminate ground water. The process includes the steps of transferring the waste solvent-containing liquid to a container and adding sufficient water so that the solvent-containing liquid has about 50% water content. Next, an absorbent blend is mixed into the liquid at the rate of about 1 lb. of blend per gallon of liquid. The blend is made up of a swellable polymer, consisting of polyacrylamide/polyacrylate copolymer salt or poly 2-propenamide-co-2-propenoic acid homopolymer salt which swells and absorbs liquid. The blend also contains a mixture of solid absorbents selected from calcium oxides, aluminum oxides, calcium sulfate, silicon oxides, pumice, perlite, activated carbon, surfactant, and ground corn cobs. The resulting mixture is stirred in the container until it becomes thick and then it is allowed to set to provide a disposable modeling clay-like solid.

Abstract: A low viscosity resin is delivered into a spent HEPA filter or other waste. The resin is introduced into the filter or other waste using a vacuum to assist in the mass transfer of the resin through the filter media or other waste.

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: The method for treating ignitable cutting swarf in accordance with the present invention involves collecting cutting swarf in a casting mold underwater and injecting a binder mixture comprising vinyl ester styrene into the vessel to fill void volume; and form a mixture comprising swarf and vinyl ester styrene; and curing the mixture. The method is especially useful for stabilizing the ignitable characteristics of radioactive zirconium cutting swarf, and can be used to solidify zirconium swarf, or other ignitable finely divided material, underwater. The process could also be performed out of water with other particulate wastes.

Abstract: The present invention provides an encapment process for rapidly stabilizing and substantially reducing the volume of moisture bearing radioactive and mixed hazardous waste materials. The present process effectively utilizes polyacrylate encapsulating material in combination with equipment or systems which deliver the encapsulates to the waste material being processed. The polyacrylates may be dispersed from a pressurized vessel to stop leaks and spills, added to solid waste material to produce waste material which has no free standing liquids, or added to liquid waste material and dried to significantly reduce the volume of the waste material and produce a waste product having no free standing liquids.

Abstract: A foamed solid product characterized in that said product is produced and prepared by a continuos process comprising mixing water permeated municipal solid waste (MSW) with a solidification reagent, wherein said solidification reagent initiates a polymerization reaction with the waste and the polymerization reaction forms a rigid polymer matrix therein. In addition, the polymer matrix also expands in volume during the polymerization reaction to form a foamed, environmentally stable, recycled solid product.

Abstract: A low-temperature method for producing coated hazardous waste pellets which re used as the aggregate in a concrete wasteform is characterized by combining hazardous waste with a chemically setting organic polymer to form a mixture which is formed into pellets. The pellets are first coated with epoxy and then coated with a silicate-based powder. The liquid concrete-pellet mixture is then placed in molds which can be rotated to concentrate the pellets away from the perimeter of the wasteform. The double-coated hazardous waste pellets have improved bonding when used as a coarse aggregate in a concrete mixture. The resulting wasteform is self-supporting and needs no external container for transportation, storage, or disposal.

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.