Embodiments of the present invention provide for assessing the state of an .sup.82Rb elution system. In certain embodiments, a system begins an assessment that comprises an elution, and a metric may be measured. This metric may be a concentration of .sup.82Rb, .sup.82Sr, or .sup.85Sr in a fluid that is eluted from the generator, the volume of the fluid that is eluted from the generator, or the pressure of the fluid flowing through at least one portion of the system. If the assessment is completed, an output may be generated on a user interface that recommends a course of action, or no course of action, based on a result of the assessment. Should the assessment not complete successfully because it is interrupted, a .sup.82Sr/.sup.82Rb generator of the system may be halted so as to prevent a user from performing an end-run around these quality control mechanisms of the .sup.82Rb elution system.

The present invention relates to a kit for radiolabelling a targeting agent with gallium-68. The present invention also relates to the use of the kit for radiolabelling a targeting agent, and a method for radiolabelling a targeting agent with gallium-68 using the kit.

The present invention relates to a kit for radiolabelling a targeting agent with gallium-68. The present invention also relates to the use of the kit for radiolabelling a targeting agent, and a method for radiolabelling a targeting agent with gallium-68 using the kit.

A method of accumulating radium radionuclides, comprising providing a first solution including thorium radionuclides and a thorium-binding extractant, wherein the first solution does not bind to radium, allowing a portion of the thorium radionuclides in the first solution to decay into radium atoms and collecting radium atoms resulting from the decay. The collected radium atoms may be included in a solution in which brachytherapy sources are dipped, in a manner which collects the radium atoms onto the source.

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) so prepared 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.

An apparatus is for the automated production of a daughter radionuclide from a parent radionuclide using a generator comprising a solid medium onto which the parent nuclide is fixed and whereby the daughter nuclide is formed by radioactive decay of the parent nuclide. The apparatus includes a fluid circuit including a chromatography column having a head port and a tail port, at least one connection port for connecting the generator to the fluid circuit, at least one inlet port for connecting fluid sources to the fluid circuit and at least one valve controlled by an electronic control unit for selectively connecting the chromatography column, the connection port and the at least one inlet port in various configurations. The various configurations include a first elution configuration for circulating an A1 solution exiting the generator and containing the daughter radionuclide, through the chromatography column from the head port to the tail port for loading the chromatography column with the daughter radionuclide; a first washing configuration for circulating an A2 washing solution from a solution inlet through the chromatography column from the head port to the tail port; and a second washing configuration for circulating an A2 washing solution from a solution inlet through the chromatography column from the tail port to the head port.

Embodiments of the present invention provide for assessing the state of an .sub.82Rb elution system. In certain embodiments, a system begins an assessment that comprises an elution, and a metric may be measured. This metric may be a concentration of .sub.82Rb, .sub.82Sr, or .sub.85Sr in a fluid that is eluted from the generator, the volume of the fluid that is eluted from the generator, or the pressure of the fluid flowing through at least one portion of the system. If the assessment is completed, an output may be generated on a user interface that recommends a course of action, or no course of action, based on a result of the assessment. Should the assessment not complete successfully because it is interrupted, a .sub.82Sr/.sub.82Rb generator of the system may be halted so as to prevent a user from performing an end-run around these quality control mechanisms of the .sub.82Rb elution system.

A .sup.68Ge/.sup.68Ga generator for a continuous production of a .sup.68Ga daughter nuclide, wherein the .sup.68Ge parent nuclide thereof is specifically adsorbed to an inorganic support material and wherein said .sup.68Ge parent nuclide continuously decays to .sup.68Ga by electron capture at a half-life of 270.82 d, wherein the inorganic support material is at least one oxide of a metal being selected from the group consisting of: Vanadium, Niobium and Tantalum. The use of at least one oxide of a metal being selected from the group consisting of: Vanadium, Niobium and Tantalum as an inorganic support material for the manufacture of a .sup.68Ge/.sup.68Ga generator for pharmaceutical purposes. With the inorganic support material of the present invention, it is possible to load .sup.68Ge/.sup.68Ga generators with up to 8000 MBq of .sup.68Ge (corresponding to 80 g Germanium).

A device and method that enables a specimen that is to be converted into a radioisotope to be inserted into an extended, retractable thimble of a nuclear reactor moveable in-core detector system and be harvested after irradiation either during reactor operation or a refueling outage without damaging the retractable thimble. The specimen is enclosed within the interior of a forward portion of a tubular member having a closed lead end and structured to travel within the retractable thimble. The tubular member is sized to extend from a position above and proximate the desired core elevation the specimen is to be irradiated at to a location above a seal table that the retractable thimble extends through. The specimen is inserted and withdrawn from the core by inserting or withdrawing the tubular member from above the seal table. Desirably, the forward end of the tubular member is divided into several specimen compartments.

There is provided a radionuclide manufacturing system, a computer-readable storage medium storing a radionuclide manufacturing program, a radionuclide manufacturing method, and a terminal device for more stably manufacturing a radionuclide.

A radionuclide manufacturing system includes: a heating unit configured to internally house a target holding a radionuclide; a gas supply unit; an adsorption unit configured to adsorb the radionuclide; a solvent supply unit; a storage unit configured to store a predetermined instruction; and a control unit configured to control the heating unit to heat the target at a temperature at which the radionuclide held in the target is allowed to volatilize, to control the gas supply unit to supply the carrier gas to the heating unit in order to transport the radionuclide volatilized in the heating unit to the adsorption unit, and to control the solvent supply unit in order to supply a solvent for eluting the radionuclide adsorbed to the adsorption unit to the adsorption unit based on the instruction.