Abstract:
A chromatographic process of producing high purity and high yield radioactive Technetium-99m. A solution containing Molybdenum-99 and Technetium-99m is placed on a chromatographic column and eluted with a neutral solvent system comprising an organic solvent and from about 0.1 to less than about 10% of water or from about 1 to less than about 70% of a solvent selected from the group consisting of aliphatic alcohols having 1-6 carbon atoms. The eluted solvent system containing the Technetium-99m is then removed leaving the Technetium-99m as a dry, particulate residue.
Abstract:
Apparatuses and methods for production of molybdenum targets, and the formed molybdenum targets, used to produce Tc-99m are described. The target includes a copper support plate having a front face and a back face. The copper support plate desirably has dimensions of thickness of about 2.8 mm, a length of about 65 mm and a width of about 30 mm; and the copper support plate desirably has either a circular or an elliptical cavity centrally formed therein by pressing molybdenum powder into the front face with a depth of about 200-400 microns. Also, the copper support plate includes cooling channels dispensed at the back face; wherein the copper support plate is water cooled by a flow of water during irradiation by a proton beam. Molybdenum powder is embedded and compressed onto the cavity of the copper support plate thereby creating a thin layer of molybdenum onto the copper support plate.
Abstract:
Disclosed are methods for recovering technetium from a highly alkaline solution. The highly alkaline solution can be a liquid waste solution from a nuclear waste processing system. Methods can include combining the solution with a reductant capable of reducing technetium at the high pH of the solution and adding to or forming in the solution an adsorbent capable of adsorbing the precipitated technetium at the high pH of the solution.
Abstract:
A spent fuel reprocessing method contacts an aqueous solution containing Technetium(V) and uranyl with an acidic solution comprising hydroxylamine hydrochloride or acetohydroxamic acid to reduce Tc(V) to Tc(II, and then extracts the uranyl with an organic phase, leaving technetium(II) in aqueous solution.
Abstract:
A method for decontaminating uranium product from the Purex process comprises addition of hydrazine to the product uranyl nitrate stream from the Purex process, which contains hexavalent (UO.sub.2.sup.2+) uranium and heptavalent technetium (TcO.sub.4 -). Technetium in the product stream is reduced and then complexed by the addition of oxalic acid (H.sub.2 C.sub.2 O.sub.4), and the Tc-oxalate complex is readily separated from the uranium by solvent extraction with 30 vol. % tributyl phosphate in n-dodecane.
Abstract translation:从Purex工艺中净化铀产品的方法包括向含有六价(UO22 +)铀和七价锝(TcO4-)的Purex工艺的硝酸铀酰产物中加入肼。 产物流中的锝减少,然后通过加入草酸(H 2 C 2 O 4)络合,并且Tc-草酸盐络合物通过溶剂萃取容易地与铀分离,30体积%。 磷酸三丁酯在正十二烷中。
Abstract:
A method for producing 99mTc may include: providing a solution comprising 100Mo-molybdate-ions; providing a proton beam having an energy suitable for inducing a 100Mo(p,2n)99mTc-nuclear reaction when exposing 100Mo-molybdate-ions; exposing the solution to the proton beams and inducing a 100Mo(p,2n)99mTc-nuclear reaction; and applying an extraction method for extracting the 99mTc from the solution. Further, a device for producing 99mTc may include: a solution with 100Mo-molybdate-ions; an accelerator for providing a proton beam with energy which is suitable for inducing a 100Mo(p,2n)99mTc-nuclear reaction when exposing 100Mo-molybdate-ions, for exposing the solution and for inducing a 100Mo(p,2n)99mTc-nuclear reaction; and an extraction step for extracting 99mTc from the solution.
Abstract:
The invention provides a method and processing system for removing both anionic and cationic technetium complexes from an aqueous solution by adjusting the pH of the solution to greater than approximately 2, and directing the solution into an integrated resin and electrochemical plating device. The integrated resin and plating device has a resin bed or resin membrane in which is disposed one or more cathodes, and one or more anodes. A potential generator produces at least a 1 volt potential between the cathodes and the anodes. As the solution passes through the resin, the technetium complexes are adsorbed onto it. When a sufficient concentration of technetium complexes is adsorbed, the plating process can atlernatively be driven to plate out the technetium onto the cathodes, or to collect various species in system anolytes/catholytes.
Abstract:
The invention relates to a process for the separation of actinides from lanthanides by the selective extraction of the actinides in an organic solvent incorporating a propane diamide.This process consists of adding to the aqueous nitric solution containing the actinides and lanthanides a thiocyanate, e.g. ammonium thiocyanate, followed by the contacting of said solution with an organic solvent incorporating at least one propane diamide, e.g. 2-tetradecyl-N,N'-dimethyl-N,N'-dibutyl-propane diamide and optionally a quaternary ammonium salt such as trilauryl methyl ammonium (TMA) thiocyanate or a mixture of quaternary ammonium thiocyanates.This leads to distribution coefficients D.sub.M for the actinides (Am) and the lanthanides (Eu, Ce) making it possible to achieve high actinide/lanthanide separation factors.
Abstract:
An initial aqueous pertechnetate solution which has a low electrolyte concentration compared with physiological saline is treated by passage through a bed of insoluble ion exchange material for adsorbing the pertechnetate. In a second step an ionic eluant having a smaller volume than the pertechnetate solution is passed through the bed to remove the pertechnetate to provide a relatively concentrated and pure eluate solution, the ion exchange material in the bed and the ionic eluant having respective properties for providing the eluate with a pH suitable for radiopharmaceutical purposes. The bed retains thereon radionuclidic impurities which may have been in the initial solution. The method can be valuable for treating the eluate from a portable technetium generator which is eluted with water and advantageously the insoluble material in the bed is zirconium oxide.