Abstract:
É descrito um equipamento para marcação de moléculas com Gálio-68 que realiza a eluição de todos os geradores de Gálio-68 disponíveis atualmente no mercado, através de um mesmo circuito de marcação (CM) de uso único que permite a purificação do material radioativo, de forma que este não possua contaminantes metálicos, como o Fe 3+ e Zn 2+ que possam prejudicar a marcação da molécula, dita purificação ocorrendo através da passagem do eluato de Gálio-68 por uma coluna cromatográfica, e um sistema de filtração esterilizante do radiofármaco marcado com Gálio-68, de forma que dito radiofármaco seja estéril e apirogênico.
Abstract:
A process for separating carbon isotopes, which comprises contacting an aqueous solution containing acid dissociation type and non-dissociation type chemical species of carbon-containing acids with a solid phase anion exchange resin to thereby simultaneously conduct a carbon isotope exchange reaction between said acid dissociation type chemical species and non-dissociation type chemical species and adsorb said acid dissociation type chemical species on said anion exchange resin, thus C12 and C13 being separated into the solution phase and the solid phase, respectively, or vice versa, for the concentration of C13. This process is extremely effective and can be conducted inexpensively as compared with conventional separating processes by chemical exchange between gas and liquid phases, between gas and solution phases, or between solution and solution phases.
Abstract:
Systems and methods for efficient, effective, and safe separation and isolation of multiple isotopes ( e.g. , Mo, Zr, Ba, Sr, Te, and lanthanide isotopes) from fission products includes use of a plurality of chromatography columns, each containing a chromatographic resin formulated to target one or more particular isotopes. The system is operable in a "series" configuration to load the multiple columns by a single pass of the sample. Then, the system may be transitioned ( e.g ., using valves) to a "parallel" configuration in which multiple columns of the system may be operated simultaneously to elute targeted isotopes. Additional parallel operations of the columns, using different eluent compositions, may be used to elute different targeted isotopes. The system may be reconditioned in preparation for a subsequent sample.
Abstract:
A process and apparatus for treating the heavy hydrogen isotope content of the contaminated water by contacting the contamined water with a molecular separation material (28) including a support medium carrying a plurality of hydration sites having associated waters of hydration, whereby a portion of the waters of hydration are replaced with heavy hydrogen isotope water molecules from the contaminated water. The hydrogen isotope water molecule content of the contaminated water is thus decreased. The molecular separation material (28) is preferably a polymer, such as a polystyrene/divinyl benzene cross-linked polymer, having hydration sites with associated waters of hydration. Preferred hydration sites are obtained by reacting the polymer which has been sulfonated or phosphonated to create reactive sites, with a salt of, for example, aluminum, sodium, magnesium, copper, zinc, cobalt, iron, nickel, manganese, potassium and chromium. Before or during contact with the molecular separation material (28), the contaminated water may be brought into contact with a separation membrane (12) selectively permeable to light water molecules relative to hydrogen isotope water molecules, to remove light water molecules from the water, thereby increasing the concentration of said hydrogen isotope molecules.
Abstract:
A process for the partial or complete simultaneous separation of isotopes of erbium, especially high thermal neutron capture cross section erbium isotopes, using continuous, steady-state, chromatography in which an ion exchange resin is the stationary phase, an aqueous solution of ions based on a mixture of erbium isotopes is the feed phase, and an aqueous acid eluant solution is the mobile phase. The process involves the mobile phase eluting or desorbing the erbium isotopic solute adsorbed on the stationary phase under conditions such that each of the various naturally occurring isotopes of erbium is primarily eluted in an elution volume distinct from the elution volumes of the other isotopes. In a preferred embodiment, the conditions are such that at least one of the elution volumes contains essentially only one isotope of erbium. The process is preferably conducted in a continuous, steady-state manner, and in particular is preferably conducted in a continuous annular chromatograph (CAC) (10).
Abstract:
The present invention relates to a method of producing and refining carrier-free lutetium-177 using chromatography, and more specifically to a method of producing and refining carrier-free lutetium 1-77 using chromatography having excellent resolution of lutetium and ytterbium without a concentration gradient of an eluent.
Abstract:
The invention provides an apparatus and system for the separation and optional analysis of the components of a sample of material, the apparatus and system comprising a cartridge comprising: at least one sample inlet port, at least one resin inlet port and a multiplicity of reagent and purge fluid input ports which are fluidically connected via a multiplicity of control valves to a multiplicity of chromatographic columns which are fluidically connected together in series; and a multiplicity of outlet ports wherein each outlet port additionally comprises an outlet valve which is adapted to control the flow of fluid through said outlet ports; wherein each of said multiplicity of chromatographic columns is aligned with one of said multiplicity of outlet ports so as to allow for fluid flow from said column through said outlet port. The system optionally additionally facilitates the analysis of the components. The invention additionally provides a method for the separation of the components of a sample of material which comprises the use of the apparatus and system of the invention. The apparatus, system and method of the invention are advantageously applied to the separation and analysis of radioactive materials.
Abstract:
A process for purification of water soluble polymers is provided. A polymer of interest can be separated from a mixture of polymers, provided the polymer of interest differs from other polymers in the mixture in the number of reactive terminal groups. The process involves derivatizing polymers at the reactive terminal groups with a derivatizing molecule, bearing either (i) two or three cationic or anionic ionizable groups, and a group capable of covalent bonding to the reactive terminal groups or (ii) three or four ionizable groups, at least one of which is capable of covalent bonding to the reactive terminal groups; followed by ion exchange. The process allows removal of PEG from MPEG, and can be used for polymers having an average size greater than 9,000 Da Derivatization may be reversible in order to allow re-use of recovered contaminant polymers.
Abstract:
A method for separating Bi from a solution of radionuclides wherein the solution contains a concentration of the chloride ions and hydrogen ions adjusted to allow the formation of a chloride complex. The solution is then brought into contact with an anion exchange resin, whereupon Bi is absorbed from the solution and adhered onto the anion exchange resin in the chloride complex. Other non-absorbing radionuclides such as Ra, Ac, and Fr, along with HCl are removed from the anion exchange resin with a scrub solution. The Bi is removed from the anion exchange resin by washing the anion exchange resin with a stripping solution free of chloride ions and with a reduced hydrogen ion concentration which breaks the chloride anionic complex, releasing the Bi as a cation. In a preferred embodiment of the present invention, the anion exchange resin is provided as a thin membrane, allowing for extremely rapid adherence and stripping of the Bi. A preferred stripping solution for purification of Bi for use in medical applications includes sodium acetate, pH 5.5. A protein conjugated with bifunctional chelating agents in vivo with the Na0Ac, to receive the Bi as it is being released from the anion exchange resin.
Abstract:
Systems, methods, and processes for a high throughput, low concentration processing of low activity tritiated light water include the electrolysis of at least some of the tritiated water to produce hydrogen and tritium gas. The hydrogen and tritium gas produced by electrolysis in some cases are combined with heated water vapor to increase throughput and passed through a liquid phase catalytic exchange column, which generally includes a catalyst that includes palladium coated with a hydrophobic polymer. As the hydrogen and tritium gas, along with heated water vapor, rise through the LPCE column, the tritium is retained on the catalyst. Deionized wash water passes down the column (i.e., in the opposite direction of the flow of the hydrogen gas and heated water vapor) and carries the retained tritium out of the LPCE column.