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.

An object of the present invention is to realize a target, for neutron-beam or proton-beam irradiation, that can withstand prolonged beam irradiation. A target for proton-beam or neutron-beam, comprising a graphite film (A) having a thermal conductivity of 500 W/mK or more in a direction parallel to an a-b plane of a graphite layer at 25° C.; and a layer (B) of a starting material for producing a radioactive substance, and being a laminate of the graphite film (A) and the layer (B). A density of the graphite film (A) is preferably 1.8 to 2.26 g/cm.sup.3. A tensile strength of the graphite film (A) is preferably 5 MPa or more.

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.

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.

A process for the separation of .sup.99mTc from molybdenum targets is described. The method for separation of .sup.99mTc isotope from molybdenum targets includes: i) providing an initial multicomponent mixture of elements, the mixture containing .sup.99mTc; ii) dissolving the multicomponent mixture of elements with an oxidizing agent to oxidize the mixture of elements; iii) heating the mixture of elements at a temperature sufficiently high enough to sublimate a vaporized compound containing .sup.99mTc; iv) condensing the vaporized compound containing .sup.99mTc to form a reaction product; v) adding a base to the condensed reaction product to dissolve the .sup.99mTc containing reaction product to form sodium pertechnetate (Na.sup.99mTcO.sub.4); and vii) purifying the crude solution of sodium pertechnetate Na.sup.99mTc04 using column chromatography to provide the .sup.99mTc isotope as a radiochemical compound.

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.

The present disclosure generally relates to methods and structures for the production of radioisotopes from the thermal neutron irradiation of selected natural isotopes. The methods, structures and operations are applicable to the production of any radioisotope that may be produced from neutron irradiation.

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.