Patent classifications
G21G1/001
Systems, apparatus and methods for separating actinium, radium, and thorium
A method of separating actinium and/or radium from proton-irradiated thorium metal. The thorium metal is irradiated to produce isotopes including thorium, actinium and/or radium. The resultant product is dissolved in solution and a selective precipitant is used to precipitate a bulk portion of the thorium. The precipitated thorium can be recovered. Chromatography is carried out on the remaining solution to remove residual thorium and to separate the actinium from the radium.
Method for producing astatine
Provided is a method capable of separating and purifying astatine-211 in a high yield and dissolving same in a solution. A method for producing astatine-211, including a step of irradiating α ray to bismuth to produce astatine-211 in the bismuth, and a step of distilling the bismuth that received α ray irradiation with a carrier gas containing an inert gas, O.sub.2 and H.sub.2O to separate and purify astatine-211, and dissolving the astatine-211 in a solution.
Purification process for the preparation of non-carrier added copper-64
Compositions comprising high levels of high specific activity copper-64, and process for preparing said compositions. The compositions comprise from about 2 Ci to about 15 Ci of copper-64 and have specific activities up to about 3800 mCi copper-64 per microgram of copper. The processes for preparing said compositions comprise bombarding a nickel-64 target with a low energy, high current proton beam, and purifying the copper-64 from other metals by a process comprising ion exchange chromatography or a process comprising a combination of extraction chromatography and ion exchange chromatography.
Process for producing radioactive dry Sn-117M tetraiodide radiochemical
Described are methods and compositions for processes of preparing a radioactive solution of Sn-117m tetraiodide. Aspects include reacting a radioactive solid Sn containing Sn-117m with a solution of I.sub.2 in an organic solvent at a temperature and for a duration sufficient to result in the formation of Sn-117m tetraiodide. Then, the organic solvent is removed by evaporation to leave dry Sn-117m tetraiodide. The organic solvent is a low boiling point solvent capable of dissolving I.sub.2 and Sn tetraiodide. The organic solvent is selected from the group consisting of an alcohol and a chlorinated solvent. In embodiments may be selected from the group consisting of dichloromethane, trichloromethane, tetrachloromethane, or mixtures thereof. In embodiments, the organic solvent excludes alcohol. The I.sub.2 may be in a slight molar excess to the radioactive solid Sn. The method may further include distilling the reactants to remove excess I.sub.2 from the distillate.
PURIFICATION PROCESS FOR THE PREPARATION OF NON-CARRIER ADDED COPPER-64
Compositions comprising high levels of high specific activity copper-64, and process for preparing said compositions. The compositions comprise from about 2 Ci to about 15 Ci of copper-64 and have specific activities up to about 3800 mCi copper-64 per microgram of copper. The processes for preparing said compositions comprise bombarding a nickel-64 target with a low energy, high current proton beam, and purifying the copper-64 from other metals by a process comprising ion exchange chromatography or a process comprising a combination of extraction chromatography and ion exchange chromatography.
Method of making an annular radioisotope target having a helical coil-shaped foil ribbon between cladding tubes
An annular radioisotope target and method therefor that includes an inner cladding tube and a helical coil-shaped foil ribbon disposed over the inner cladding tube. The helical coil-shaped foil ribbon has a first end, a second end, a first edge and a second edge. An outer cladding tube is disposed over the helical coil-shaped foil ribbon and inner cladding tube, and end caps are attached to the outer cladding tube and the inner cladding tube.
Target irradiation systems for the production of radioisotopes
A target irradiation system for irradiating a radioisotope target in a vessel penetration of a fission reactor, includes a target delivery assembly with a body defining a central bore, a basket that is slidably receivable within the central bore of the body, and a winch that is connected to the basket by a cable. The target delivery assembly is affixed to the vessel penetration of the reactor; and a target passage is in fluid communication with the target delivery assembly. The basket is configured to receive a radioisotope target therein via the target passage and be lowered into the vessel penetration of the reactor when irradiating the radioisotope target. The target delivery system forms a portion of the pressure boundary of the reactor when in fluid communication with the reactor.
Method for producing .SUP.225.Ac
A method for producing 225.sup.A including: a method (X) for purifying a .sup.226Ra-containing solution, including an adsorption step of allowing a .sup.226Ra ion to adsorb onto a carrier having a function of selectively adsorbing a divalent cation by bringing a .sup.226Ra-containing solution into contact with the carrier under an alkaline condition, and an elution step of eluting the .sup.226Ra ion from the carrier under an acidic condition; a method for producing a .sup.226Ra target, including an electrodeposition liquid preparation step of preparing an electrodeposition liquid by using a purified .sup.226Ra-containing solution obtained by the method (X), and an electrodeposition step of electrodepositing a .sup.226Ra-containing substance on a substrate by using the electrodeposition liquid; and a step of irradiating a .sup.226Ra target produced by the method for producing a .sup.226Ra target with at least one selected from a charged particle, a photon, and a neutron by using an accelerator.
PURIFICATION PROCESS FOR THE PREPARATION OF NON-CARRIER ADDED COPPER-64
Compositions comprising high levels of high specific activity copper-64, and process for preparing said compositions. The compositions comprise from about 2 Ci to about 15 Ci of copper-64 and have specific activities up to about 3800 mCi copper-64 per microgram of copper. The processes for preparing said compositions comprise bombarding a nickel-64 target with a low energy, high current proton beam, and purifying the copper-64 from other metals by a process comprising ion exchange chromatography or a process comprising a combination of extraction chromatography and ion exchange chromatography.
Purification process for the preparation of non-carrier added copper-64
Compositions comprising high levels of high specific activity copper-64, and process for preparing said compositions. The compositions comprise from about 2 Ci to about 15 Ci of copper-64 and have specific activities up to about 3800 mCi copper-64 per microgram of copper. The processes for preparing said compositions comprise bombarding a nickel-64 target with a low energy, high current proton beam, and purifying the copper-64 from other metals by a process comprising ion exchange chromatography or a process comprising a combination of extraction chromatography and ion exchange chromatography.