Provided herein are methods of isolating and using radioactive mercury. In particular, provided herein are methods of isolating radioactive mercury including the use of a thiacrown ether, and using the isolated radioactive mercury in therapeutic and/or imaging applications.

The present disclosure relates in general to nuclear medicine and generators for the production of radiopharmaceuticals for medical use. In particular, present disclosure relates to a generator column that resists high heat such as depyrogenation and sterilization. This allows some steps of the preparation of the column to be performed in a non-sterile environment. This also allows the generator column to be reusable. The present disclosure further describes methods for the preparation of a generator where a parent radioisotope is charged on the column matrix before or after the matrix is loaded in the column.

The present disclosure relates in general to nuclear medicine and generators for the production of radiopharmaceuticals for medical use. In particular, present disclosure relates to a generator column that resists high heat such as depyrogenation and sterilization. This allows some steps of the preparation of the column to be performed in a non-sterile environment. This also allows the generator column to be reusable. The present disclosure further describes methods for the preparation of a generator where a parent radioisotope is charged on the column matrix before or after the matrix is loaded in the column.

The present disclosure relates in general to nuclear medicine and generators for the production of radiopharmaceuticals for medical use. In particular, present disclosure relates to a generator column that resists high heat such as depyrogenation and sterilization. This allows some steps of the preparation of the column to be performed in a non-sterile environment. This also allows the generator column to be reusable. The present disclosure further describes methods for the preparation of a generator where a parent radioisotope is charged on the column matrix before or after the matrix is loaded in the column.

Infusion system configurations and assemblies facilitate routing of infusion circuit tubing lines. Tubing lines are routed into and out from compartments of a shielding assembly for the infusion system, at locations which prevent kinking and/or crushing of the lines, and/or provide for ease in assembling the circuit. A plurality of the lines may be held together by a support frame to form a disposable infusion circuit subassembly, that can further facilitate routing of the lines.

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.

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.99mTcO.sub.4 using column chromatography to provide the .sup.99mTc isotope as a radiochemical compound.

A system and method for automatic production of astatine-211 labeled molecules is described. The invention represents a significant advantage in the preparation of At-211 radiopharmaceuticals including better reproducibility, reduced production time and increased radiation safety. The invention also enables routine automatic synthesis of radiopharmaceuticals in a clinical setting, in conjunction or at short distance from a cyclotron unit capable of producing the radionuclide.

A method for producing an iodine radioisotopes fraction, comprising the steps of dissolving enriched uranium targets forming a slurry, filtering said slurry, absorbing salts of iodine radioisotopes on an aluminium resin doped with silver and recovering said iodine radioisotopes fraction, is disclosed. The recovery of the iodine radioisotopes fraction, in particular of I-131, comprises washing the aluminium resin doped in silver using a solution of NaOH and eluting of iodine radioisotopes by a solution of thiourea, and collecting an eluate containing said iodine radioisotopes in a thiourea solution.

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.