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 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 .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 .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 radioactive fine particle manufacturing system to manufacture physically stable radioactive fine particles without using large-scale equipment, which enable performance evaluation of a radioactivity measuring instrument employing a novel physical indicator, with which a method for controlling radioactivity concentration by means of the humidity of air is presented in a specific manner, and with which it is possible to implement performance evaluation of the overall radioactivity measuring instrument. The radioactive fine particle manufacturing system uses a configuration provided with a radioactive gas generating system, a specific particle-sized aerosol generating system and a mixing chamber, to manufacture radioactive fine particles employing natural radioactive nuclides. 220 Rn is employed to manufacture radioactive fine particles using physically stable progeny nuclides. In the mixing chamber, the progeny nuclides are caused to attach only to an aerosol having a specific particle size, to generate radioactive fine particles having a specific particle size.

A radioactive fine particle manufacturing system to manufacture physically stable radioactive fine particles without using large-scale equipment, which enable performance evaluation of a radioactivity measuring instrument employing a novel physical indicator, with which a method for controlling radioactivity concentration by means of the humidity of air is presented in a specific manner, and with which it is possible to implement performance evaluation of the overall radioactivity measuring instrument. The radioactive fine particle manufacturing system uses a configuration provided with a radioactive gas generating system, a specific particle-sized aerosol generating system and a mixing chamber, to manufacture radioactive fine particles employing natural radioactive nuclides. 220 Rn is employed to manufacture radioactive fine particles using physically stable progeny nuclides. In the mixing chamber, the progeny nuclides are caused to attach only to an aerosol having a specific particle size, to generate radioactive fine particles having a specific particle size.

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 .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).

An isotope production system, emanation generator, and process are disclosed for production of high-purity radioisotopes. In one implementation example, high-purity Pb-212 and/or Bi-212 isotopes are produced suitable for therapeutic applications. In one embodiment the process includes transporting gaseous radon-220 from a radium-224 bearing generator which provides gas-phase separation of the Rn-220 from the Ra-224 in the generator. Subsequent decay of the captured Rn-220 accumulates high-purity Pb-212 and/or Bi-212 isotopes suitable for direct therapeutic applications. Other high-purity product isotopes may also be prepared.

An isotope production system, emanation generator, and process are disclosed for production of high-purity radioisotopes. In one implementation example, high-purity Pb-212 and/or Bi-212 isotopes are produced suitable for therapeutic applications. In one embodiment the process includes transporting gaseous radon-220 from a radium-224 bearing generator which provides gas-phase separation of the Rn-220 from the Ra-224 in the generator. Subsequent decay of the captured Rn-220 accumulates high-purity Pb-212 and/or Bi-212 isotopes suitable for direct therapeutic applications. Other high-purity product isotopes may also be prepared.