Patent classifications
G21G1/00
Separation of Radiometals
Method of separation of a radiometal ion from a target metal ion, comprising a first liquid-liquid extraction step in which an organic phase comprising an extractant and an interfacial tension modifier is mixed with an aqueous phase comprising the radiometal ion and the target metal ion in order that the radiometal ion is at least partially transferred to the organic phase, followed by a first phase separation step, wherein the phase separation is carried out in flow comprising the use of a microfiltration membrane to separate the phases based on the interfacial tension between the phases such that a permeate phase passes through the membrane and a retentate phase does not.
Method and Apparatus for Production of Actinium 225 Isotope
In one illustrative embodiment, a target insert for the production of Ac-225 in a particle accelerator is disclosed which may include a metal body comprising a central flat area deposition of Ra-226 or any means of depositing Ra226 on target body, a channel surrounding the perimeter of the central flat area and a hollow section opposite the central flat area. The target insert also includes an area of Ra-226 disposed on the central flat area and a protective layer disposed atop the area of Ra-226 and conforming to the metal target such that the protective layer is also disposed onto the channel surrounding the perimeter of the central flat area. A crimp ring is disposed on top of the protective layer in the channel surrounding the perimeter of the central flat area, wherein the crimp ring has been compressed to fill the channel and seal the protective layer to the metal body.
Method and Apparatus for Production of Actinium 225 Isotope
In one illustrative embodiment, a target insert for the production of Ac-225 in a particle accelerator is disclosed which may include a metal body comprising a central flat area deposition of Ra-226 or any means of depositing Ra226 on target body, a channel surrounding the perimeter of the central flat area and a hollow section opposite the central flat area. The target insert also includes an area of Ra-226 disposed on the central flat area and a protective layer disposed atop the area of Ra-226 and conforming to the metal target such that the protective layer is also disposed onto the channel surrounding the perimeter of the central flat area. A crimp ring is disposed on top of the protective layer in the channel surrounding the perimeter of the central flat area, wherein the crimp ring has been compressed to fill the channel and seal the protective layer to the metal body.
Method of producing TC-99M by using nuclear resonance fluorescence
Disclosed is a method of producing Tc-99m by using nuclear resonance fluorescence. More specifically, and a method of preparing Tc-99m by using nuclear resonance fluorescence includes irradiating a ground-state Tc-99 nucleus with a photon beam, thereby causing a nuclear transmutation to proceed such that the nucleus excited to high energy and then undergoes a transition to Tc-99m.
Methods for purifying molybdenum-99
Methods for purifying the molybdenum-99 isotope are disclosed. Molybdenum-99 is loaded onto an anion exchange column and extracted. In some embodiments, the extraction solution may include nitric acid and nitrate salts. In other embodiments, a two stage elution is performed in which a nitric acid containing eluent and a hydroxide containing eluent are used in succession to extract molybdenum-99.
Method for producing a fraction of Xenon radioisotopes, in particular Xe-133, fraction of Xenon radioisotopes, in particular Xe-133
A method for producing a fraction of xenon radioisotopes, comprising the steps of dissolving enriched uranium targets forming a slurry and a gaseous phase containing xenon radioisotopes, isolating the xenon radioisotopes using zeolite doped with silver, preferably chosen from the group consisting of aluminosilicates doped with silver, titanosilicates doped with silver and mixtures thereof, and recovering the fraction of xenon radioisotopes, in particular Xe-133.
METHOD FOR PREPARING AT LEAST ONE GENERATOR WITH A HIGH RADIUM-228 CONTENT
A method for preparing one or more generators with a high radium-228 content from an aqueous solution comprising thorium-232 and radium-228. The generator(s) can be used, in particular, for producing thorium-228, from which radium-224, then lead-212 and bismuth-212 can be obtained. The method and the generator(s) that it can be used to prepare are therefore applicable, in particular, in the manufacture of radiopharmaceuticals made from lead-212 or bismuth-212, which can be used in nuclear medicine and, in particular, in targeted alpha radiotherapy for the treatment of cancers.
APPARATUS FOR PRODUCING COPPER-67 RADIOISOTOPE FOR MEDICAL APPLICATIONS
The present invention provides a target unit and a sublimation apparatus suitable for use in a method for producing Cu67 radioisotope suitable for use in medical applications. The apparatus comprises a sublimation tube with one open end. The sublimation tube contains an ingot comprising Zn68 and Cu67 in a ceramic capsule contacting a closed end the sublimation tube. A removable vacuum dome is sealable over the open end of the sublimation tube so that interior of the apparatus can be placed under vacuum.
SYSTEM AND METHOD OF RECOVERING A PARENT RADIONUCLIDE FROM A RADIONUCLIDE GENERATOR
A method for recovering a parent radionuclide from a radionuclide generator is disclosed where the parent radionuclide is adsorbed to a stationary phase. The method contains a series of elutions. At least one elution is with an alcohol. At least one elution with water. At least one elution is with a mineral acid other than hydrochloric acid that is paused to soak the stationary phase with the mineral acid.
Compact assembly for production of medical isotopes via photonuclear reactions
The invention provides a method for generating medical isotopes, the method comprising contacting a primary radiation beam with a converter for a time sufficient to produce a secondary beam of gamma particles, and contacting the beam of gamma particles to a target, where the cross section dimension of the beam of gamma particles is similar to the cross section dimension of the target. Both the converter and target are small in diameter and very closely spaced. Also provided is a system for producing medical isotopes, the device comprising a housing having a first upstream end and a second downstream end, a radiotransparent channel (collimator) with a first upstream end and a downstream end, wherein the upstream end is adapted to receive a radiation beam, a target positioned downstream of the downstream end of the channel and coaxially aligned with the channel, wherein the target has a cross section that is similar to the cross section of the channel.