The present disclosure provides a method of separating Mo-99 from W-187 from a solution comprising Mo-99 and W-187. The method comprises contacting a tridentate diglycolanude ligand with a solution comprising Mo-99 and W-187 and eluting W-187 from the tridentate diglycolanude ligand to thereby an eluate comprising W-187.

Methods for rapid isolation of radionuclides (e.g., .sup.68Ga) produced using a cyclotron and methods for recycling of the parent isotope (e.g., .sup.68Zn) are disclosed. In one version of the method, a solution including a radionuclide (e.g., .sup.68Ga) is created from a target including cations (e.g., .sup.68Zn). The solution including the radionuclide is passed through a first column including a sorbent comprising a hydroxamate resin to adsorb the radionuclide on the sorbent, and the radionuclide is eluted off the sorbent. The cations (e.g., .sup.68Zn) are recovered from a recovery solution that has passed through the first column by passing the recovery solution through a second column including a second sorbent comprising a cation exchange resin.

The present disclosure provides a composition that includes a mixture of (i) radioactive microparticles; and (ii) non-radioactive microparticles. The radioactive microparticles may be suitable to treat a vascularized tumour, such as a liver tumour or a metastasized liver tumour. The radioactive microparticles and the non-radioactive microparticles may have substantially the same resistance when flowing in a liquid through a conduit. The present disclosure also provides methods of making and methods of using mixtures of microparticles.

The invention relates to a method and a system for producing radioisotopes, and specifically, the method and system for producing radioisotopes including generating one or more among actinium-225 (.sup.225Ac), thorium-227 (.sup.227Th), and radium-226 (.sup.226Ra) by irradiating a natural thorium target including thorium-232 (.sup.232Th) with braking radiation or an accelerated electron beam.

A method of producing actinium by using liquefied radium includes producing Ac-225 using Ra-226 of a liquefied state, moving the produced Ac-225 in a liquefied state after Ac-225 is produced, and separating Ac-225 and reusing Ra-226. As a result, a nuclear reaction process of Ac-225 may be performed and loss of Ra-226 may be minimized. Further, such a method may improve safety by including a radon collection unit which is capable of discharging and isolating radon produced from Ra-226, thereby preventing radiation exposure due to radon.

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.

Method for the manufacture of Radium-225-containing material from Radium-226-containing materials by subjecting a starting material containing Radium-226 to neutron irradiation from a nuclear reactor to convert .sup.226Ra into Radium-225 to provide a Radium-225-containing material, characterised in that the neutron irradiation of Radium-226-containing starting material is performed in a moderated nuclear reactor; and the Radium-226-containing starting material is shielded with a thermal neutron absorption shield.

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.

The widespread utilization and growing demand for radiopharmaceuticals are attributable to the development and availability of a range of radiopharmaceuticals. The present disclosure describes methods of making 3-dimensional nano-porous, micro-porous, meso-porous, or macro-porous materials. The present disclosure also describes methods of irradiating and separating isotopes using the 3-dimensional nano-porous, micro-porous, meso-porous, or macro-porous materials.

There is provided a method of producing a radioisotope with a production time shortened. There is provided a producing method of a radioisotope, the method including: irradiating a target substance with a radiation beam; and extracting the radioisotope which is generated by irradiating the target substance and flowing a gas over the substance to transport the radioisotope in gas phase toward an outlet.