Abstract: A method for the manufacture of highly purified 68Ge material for radiopharmaceutical purposes. The invention particularly concerns the production of 68Ge-API (API=Active Pharmaceutical Ingredient) solution complying with the Guidelines for good manufacturing practices (GMP). Starting material for the method of the present invention can be a 68Ge stock solution of commercial or other origin as raw material. Such 68Ge containing raw solutions are purified from potential metal and organic impurities originating from production processes. The radiochemical method disclosed is based on a twofold separation of 68Ge from organic and metallic impurities with two different adsorbent materials. During the first separation phase 68Ge is purified from both organic and metallic impurities by adsorption in germanium tetrachloride form, after which hydrolyzed 68Ge is purified from remaining metallic impurities by cation exchange. The final 68Ge-API-product e.g.

Abstract: A method for the manufacture of highly purified 68Ge material for radiopharmaceutical purposes. The invention particularly concerns the production of 68Ge-API (API=Active Pharmaceutical Ingredient) solution complying with the Guidelines for good manufacturing practices (GMP). Starting material for the method of the present invention can be a 68Ge stock solution of commercial or other origin as raw material. Such 68Ge containing raw solutions are purified from potential metal and organic impurities originating from production processes. The radiochemical method disclosed is based on a twofold separation of 68Ge from organic and metallic impurities with two different adsorbent materials. During the first separation phase 68Ge is purified from both organic and metallic impurities by adsorption in germanium tetrachloride form, after which hydrolyzed 68Ge is purified from remaining metallic impurities by cation exchange. The final 68Ge-API-product e.g.

Abstract: A 68Ge/68Ga generator for a continuous production of a 68Ga daughter nuclide, wherein the 68Ge parent nuclide thereof is specifically adsorbed to an inorganic support material and wherein said 68Ge parent nuclide continuously decays to 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 68Ge/68Ga generator for pharmaceutical purposes. With the inorganic support material of the present invention, it is possible to load 68Ge/68Ga generators with up to 8000 MBq of 68Ge (corresponding to 80 ?g Germanium).

Abstract: A 68Ge/68Ga generator for a continuous production of a 68Ga daughter nuclide, wherein the 68Ge parent nuclide thereof is specifically adsorbed to an inorganic support material and wherein said 68Ge parent nuclide continuously decays to 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 68Ge/68Ga generator for pharmaceutical purposes. With the inorganic support material of the present invention, it is possible to load 68Ge/68Ga generators with up to 8000 MBq of 68Ge (corresponding to 80 ?g Germanium).

Abstract: The present invention relates to a column chromatographic method of manufacturing non-carrier-added high-purity 177Lu compounds for medicinal purposes. In the method in accordance with the invention a cation exchanger and a suitable chelating agent are used. With the method in accordance with the invention it is possible for the first time to provide non-carrier-added high-purity 177Lu compounds in milligram amounts for pharmaceutical-medicinal purposes from 176Yb compounds irradiated with thermal neutrons, the radionuclides 177Lu and 176Yb being present in an approximate mass ratio of 1:102 to 1:1010 for purification.

Abstract: An applicator for applying a radioactive substance to a biological tissue, the applicator comprising a container for receiving the radioactive substance; an application device connectable to the container, by which the substance compound can be applied to the tissue; and at least a part of a conveying device by which the radioactive substance can be supplied from the container into the application device when the application device has been connected to the container.

Abstract: The present invention relates to a column chromatographic method of manufacturing non-carrier-added high-purity 177Lu compounds for medicinal purposes. In the method in accordance with the invention a cation exchanger and a suitable chelating agent are used. With the method in accordance with the invention it is possible for the first time to provide non-carrier-added high-purity 177Lu compounds in milligram amounts for pharmaceutical-medicinal purposes from 176Yb compounds irradiated with thermal neutrons, the radionuclides 177Lu and 176Yb being present in an approximate mass ratio of 1:102 to 1:1010 for purification.

Abstract: The present invention refers to a method for producing a radium target for the production of radionuclides by means of accelerated protons, whereby at least one radium containing material out of an aqueous-organic solution or suspension of such a material is applied by means of a dispersing device on a surface in such a way that the dispersing device and the surface are moving relatively towards each other and that the solvent is removed substantially spontaneously. Further, the invention refers to a radium target that is created in such a way that it may exhibit an activity of up to 1.5 curie. The radium targets according to the present invention serve for the production of the radionuclide 225Ac, which may be used in nuclear medicine in the treatment of cancer, particularly in form of its daughter nuclide 213Bi.

Abstract: An applicator for applying a radioactive substance to a biological tissue, the applicator comprising a container for receiving the radioactive substance; an application device connectable to the container, by which the substance compound can be applied to the tissue; and at least a part of a conveying device by which the radioactive substance can be supplied from the container into the application device when the application device has been connected to the container.

Abstract: The invention relates to an apparatus for preparing a small amount of a radioactive substance combination, including a one-part body, a mixing device integrated in the body and adapted to receive a small amount of chemical substances, and at least one receptacle integrated in the body and connected to the mixing device and adapted to hold a small amount of a chemical substance.

Abstract: The invention relates to an apparatus for preparing a small amount of a radioactive substance combination, including a one-part body, a mixing device integrated in the body and adapted to receive a small amount of chemical substances, and at least one receptacle integrated in the body and connected to the mixing device and adapted to hold a small amount of a chemical substance.

Abstract: The present invention refers to a method for producing a radium target for the production of radionuclides by means of accelerated protons, whereby at least one radium containing material out of an aqueous-organic solution or suspension of such a material is applied by means of a dispersing device on a surface in such a way that the dispersing device and the surface are moving relatively towards each other and that the solvent is removed substantially spontaneously. Further, the invention refers to a radium target that is created in such a way that it may exhibit an activity of up to 1.5 curie. The radium targets according to the present invention serve for the production of the radionuclide 225Ac, which may be used in nuclear medicine in the treatment of cancer, particularly in form of its daughter nuclide 213Bi.

Abstract: The present invention relates to a radium target as well as to a method for producing it for the production of radionuclides by means of accelerated protons, wherein an electrodeposition of radium out of at least one aqueous organic solution containing 226Ra ions is carried out on at least one aluminium surface, wherein the aluminium surface is connected as cathode. With the 226Ra target according to the present invention, 225Ac/213Bi, which can be used, for example, for radioimmunotherapy for cancer treatment, can be produced continuously and in sufficient quantities at a reasonable price.