摘要:
A process for the recovery of a radioisotope from a waste resin of a nuclear power plant comprises the steps of: a) treating a waste resin loaded with at least one radioisotope with an organic acid or alkaline compound to release the at least one radioisotope and to obtain a process solution containing the at least one radioisotope; b) separating the at least one radioisotope from the process solution through a reaction specific to the radioisotope so as to obtain a treated process solution depleted of the at least one radioisotope, wherein said depleted process solution comprises the organic acid or alkaline compound and optionally a non-reacted radioisotope; c) reacting the organic acid or alkaline compound in the depleted process solution from step b) by thermal and/or photochemical oxidation to form gaseous reaction products; and d) reloading the waste resin with the reacted process solution from step c) to bind the non-reacted radioisotope on the waste resin. Further, an apparatus is provided to carry out the above method.
摘要:
The present invention is a method for eliminating radioactive iodine using a hydrophilic resin that adsorbs radioactive iodine, wherein the hydrophilic resin is at least one selected from the group consisting of a hydrophilic polyurethane resin, a hydrophilic polyurea resin, and a hydrophilic polyurethane-polyurea resin and has a hydrophilic segment and, in the principal chain and/or a side chain in the structure thereof, has a tertiary amino group or has a tertiary amino group and polysiloxane segment. By means of the present invention, a novel method for eliminating radioactive iodine is provided that is simple and low-cost, furthermore does not require an energy source such as electricity, moreover can take in and stably immobilize the eliminated radioactive iodine within a solid, and is capable of reducing the volume of radioactive waste as necessary.
摘要:
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.
摘要:
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.
摘要:
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.
摘要:
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.
摘要:
There is disclosed a method and apparatus for waste disposal by hydraulic embedment in a subterranean formation. A method in accordance with the present invention comprises the steps of drilling into stable geologic formations thousands of feet below ground, fracturing those formations, pumping a mixture of hazardous waste in solid, liquid, or sludge form and a selected transport medium into the fractured formations, and preventing migration of the waste. Although a suitable transport medium can be selected based on a number of factors, transport media selected in accordance with one aspect of the present invention prevent migration of the waste by reacting chemically or to either heat or pressure or both to become highly viscous or solid. In other aspects of the present invention, the method prevents waste migration by either pumping a fluid for sealing the fractured underground formation before the mixture is pumped or encapsulating the waste prior to mixture with the transport medium and injection into the fractured formation. Apparatus for carrying out the method is also disclosed.
摘要:
A method for long-term storage of radioactive waste in a solid bitumen is here taught. A granular ion-exchange resin (including radioactive ions) is mixed with a bitumen and water emulsion to produce a swollen aqueous product for encapsulation. The method is carried out at room temperature and optionally includes a cationic emulsion having a pH value of less than 4. The emulsion has a water content form 15-50% by weight and preferably is saturated with the water.
摘要:
Method for the final conditioning of radioactive and/or toxic waste by fusing it into thermoplastic matrix material, binding radioactive and/or toxic pollutants contained in the waste from all sides, characterized by the feature that radioactive thermoplastic synthetic material is used as the thermoplastic matrix material.
摘要:
A cartridge for the permanent storage and disposal of radioactive particulate waste composed of a liquid impervious casing enclosing a waste storage region provided with a ferromagnetic matrix made of steel wool, together with inlet and outlet conduits suitably associated with the waste storage region to enable a liquid containing such waste material to be conducted through the matrix while the particulate waste is adhered thereto under the influence of a magnetic field and the remaining liquid filtrate is expelled from the cartridge, and to then permit an encapsulating material, such as a resin-catalyst mixture, to be introduced into the waste storage region to completely fill that region. The cartridge is temporarily connected into a system including remotely controllable valves and conduits for permitting the liquid containing waste material to be introduced into the cartridge while the liquid component thereof is removed to a storage container, and the encapsulating material to be then introduced into the waste storage region, followed by direct insertion of the cartridge into a drum which can be subsequently sealed and permanently stored, all of this occurring in a fully mechanized and remote manner which does not require the exposure of any operating personnel to significant radiation dose.