摘要:
A receptor for the simultaneous removal of oxoanions and their counterions from aqueous phase, particularly containing radioactive wastes, containing amide groups specifically coordinating the oxoanions, as well as moieties specifically coordinating cations, according to the present invention is characterised in that it contains within one molecule domains binding oxoanions and domains binding cations, preferably adapting a molecular structure of a general formula: (I) wherein Z this is a group containing crown ether, preferably a benzocrown group, X is any substituent, including the Y—Z grouping, and Y is any substituent or 0 (i.e. a direct bond between N and Z), where the oxoanion binding domain is a squaramide unit coordinating the oxoanions through amide groups, and squaramide contains additional substituents that increase or decrease the acidity of its amide protons, compared to unsubstituted squaramide, whereas the counter ion binding domain is a crown ether of a size adjusted to the type of binding cation, which forms part of at least one of the aforementioned substituents of squaramide, where the receptor has the ability to remove oxoanions and their counterions from aqueous phase to another water-immiscible phase, preferably to organic phase, and has the ability to form soluble complexes in at least one of the aforementioned phases. The invention considers also a method of removing oxoanions in the form of inorganic salts from aqueous phase, using receptors of the invention in the form of organic molecules containing amide groups, according to the invention is characterised in that it uses the aforementioned receptors for simultaneous binding of oxoanions and their counterions in aqueous phase, preferably acidic when using the receptor with substituents increasing acidity of squaramide protons, or alkaline when using the receptor with substituents decreasing acidity of squaramide protons. A sensor for detecting oxoanions according to the invention is characterised in that it uses the aforementioned receptors, dissolved or suspended in an organic solvent or in a mixture of organic solvents, forming coloured complexes in contact with the phase containing given oxoanions. The preparation for removing oxoanions from aqueous solutions, particularly containing radioactive waste at the stage preceding their disposal by vitrification, is characterised in that it contains the receptor according to the invention, dissolved or suspended in the water-immiscible phase, and the appropriate amount of counterion facilitating extraction. A process of utilisation of aqueous solutions by vitrification, particularly solutions containing radioactive waste, is characterised in that vitrification step is preceded by the step of oxoanions removal, preferably sulfate(VI) anions, by the method according to the invention, using the receptors according to the invention, preferably using the preparation according to the invention.
摘要:
Apparatuses, processes and methods for the separation, isolation, or removal of radioactive isotopes from liquid radioactive waste, these processes and methods employing a plurality of microspheres. In some embodiments, the processes and methods further include the vitrification of the separated isotopes, generally with the plurality of microspheres. Vitrification is often a step in a larger scheme of preparing the radioactive isotopes for long-term storage or other disposition.
摘要:
A method for immobilizing liquid radioactive waste is provided, the method having the steps of mixing waste with polymer to form a non-liquid waste; contacting the non-liquid waste with a solidifying agent to create a mixture, heating the mixture to cause the polymer, waste, and filler to irreversibly bind in a solid phase, and compressing the solid phase into a monolith. The invention also provides a method for immobilizing liquid radioactive waste containing tritium, the method having the steps of mixing liquid waste with polymer to convert the liquid waste to a non-liquid waste, contacting the non-liquid waste with a solidifying agent to create a mixture, heating the mixture to form homogeneous, chemically stable solid phase, and compressing the chemically stable solid phase into a final waste form, wherein the polymer comprises approximately a 9:1 weight ratio mixture of styrene block co-polymers and cross linked co-polymers of acrylamides.
摘要:
A method for immobilizing liquid radioactive waste is provided, the method having the steps of mixing waste with polymer to form a non-liquid waste; contacting the non-liquid waste with a solidifying agent to create a mixture, heating the mixture to cause the polymer, waste, and filler to irreversibly bind in a solid phase, and compressing the solid phase into a monolith. The invention also provides a method for immobilizing liquid radioactive waste containing tritium, the method having the steps of mixing liquid waste with polymer to convert the liquid waste to a non-liquid waste, contacting the non-liquid waste with a solidifying agent to create a mixture, heating the mixture to form homogeneous, chemically stable solid phase, and compressing the chemically stable solid phase into a final waste form, wherein the polymer comprises approximately a 9:1 weight ratio mixture of styrene block co-polymers and cross linked co-polymers of acrylamides.
摘要:
A method for processing a radioactive liquid waste containing boron of the present invention includes: a molar ratio control step of adding an alkali metal or an alkali metal compound to a radioactive liquid waste containing boron to control an alkali metal/boron molar ratio in the radioactive liquid waste to be 0.8 or more; a drying step of drying the radioactive liquid waste having the controlled molar-ratio using a dryer to form a powdered waste; a dissolving step of mixing the powdered waste with kneading water to prepare a solution; and a kneading step of adding a hydraulic inorganic solidifying material to the solution, and kneading the hydraulic inorganic solidifying material and the solution for solidification.
摘要:
A solidification method of radioactive waste is provided, including kneading a binder and an inorganic adsorbent to obtain a kneaded object, the in organic adsorbent included radionuclides; extruding the kneaded object to obtain an extruded material object; cutting the extruded material object to obtain at least one extruded material block; and firing the at least one extruded material block to solidify the at least one extruded material block.
摘要:
A method of immobilizing a radioisotope and vitrified chemically bonded phosphate ceramic (CBPC) articles formed by the method are described. The method comprises combining a radioisotope-containing material, MgO, a source of phosphate, and optionally, a reducing agent, in water at a temperature of less than 100° C. to form a slurry; curing the slurry to form a solid intermediate CBPC article comprising the radioisotope therefrom; comminuting the intermediate CBPC article, mixing the comminuted material with glass frits, and heating the mixture at a temperature in the range of about 900 to about 1500° C. to form a vitrified CBPC article comprising the radioisotope immobilized therein.
摘要:
A method of immobilizing a radioisotope and vitrified chemically bonded phosphate ceramic (CBPC) articles formed by the method are described. The method comprises combining a radioisotope-containing material, MgO, a source of phosphate, and optionally, a reducing agent, in water at a temperature of less than 100° C. to form a slurry; curing the slurry to form a solid intermediate CBPC article comprising the radioisotope therefrom; comminuting the intermediate CBPC article, mixing the comminuted material with glass frits, and heating the mixture at a temperature in the range of about 900 to about 1500° C. to form a vitrified CBPC article comprising the radioisotope immobilized therein.
摘要:
A composition of matter includes water, at least one acid, at least one surfactant, at least one fluoride salt, and ammonium nitrate. A method of decontaminating a surface includes exposing a surface to such a composition and removing the composition from the surface. Other compositions of matter include water, a fatty alcohol ether sulfate, nitrilotriacetic acid, at least one of hydrochloric acid and nitric acid, sodium fluoride, potassium fluoride, ammonium nitrate, and gelatin.
摘要:
Methods are described for the removal of highly soluble radioactive anions, e.g., radioactive technetium and/or radioiodide, from an aqueous solution. The methods utilize a sequestering agent that includes an organoclay, i.e., a clay with an intercalated cationic quaternary amine, as a sorbent for highly soluble radioactive anions that are present within an aqueous solution. In exemplary embodiments, the method can be utilized to treat aqueous waste at a nuclear power facility or to treat a groundwater contamination site or a soil or sediment contaminated site.