[en] The description is given of a rechargeable radioactive isotope generator having the following features: a box containing a transport shield, a shielded generator including elements for the absorption and holding of the parent isotope, an eluant tank, a first pipe causing this tank to communicate with the transport shield, a second pipe causing this transport shield to communicate with the shielded generator and a third pipe placing the shielded generator in communication with the outside of the unit. It also includes a shelf across the external front part of the unit a part of which is shielded by external components, a shielded elution flask in which the eluate is poured and a filter set at a point between the flask and the third pipe

[en] The system consists of a rechargeable generator to produce ⁹⁹mTc from its mother isotope ⁹⁹Mo and a shield for shipping purposes. This shield contains a vial or ampoule with the mother isotope to be newly applied. The septum of the vial can be perforated and the isotope be transferred into the generator without the operator needing to touch the vial or remove it from its shipping protection (made of Pb). The casing of the system consists of stainless steel. (DG)

[en] A rechargeable radioisotope generator system is described in which the transfer of the parent isotope, molybdenum 99, can be affected safely and easily. Part of the system consists of a shielded shipping vial for the parent isotope. The generator consists of an alumina column upon which molybdenum 99 may be adsorbed and from which technetium 99m may be eluted. The generator is shipped as a cold package to the user and is charged as needed. A transfer mechanism is incorporated in the shipping shield, which allows the septum of the vial to be pierced and the contents to be transferred to the generator essentially automatically. (LL)

[en] This patent describes a radioactive suspension for treatment of arthritis. It includes a ¹²¹Tin compound in aggregation with ferric hydroxide

[en] A radioactive composition is described for the treatment of arthritis comprising, in combination, a ferric hydroxide or aluminum hydroxide aggregate suspension having a particle size of 3 to 20 microns, wherein a radionuclide is entrapped, the radionuclide being /sup 166/Holmium

No abstract available

[en] A primary target for the production of fission products in a nuclear reactor, such as uranium or plutonium fission products, is comprised of an enclosed, cylindrical vessel, preferably comprised of stainless steel, having a thin, continuous, uniform layer of fissionable material, integrally bonded to its inner walls and a port permitting access to the interior of the vessel. A process is also provided for depositing uranium material on to the inner walls of the vessel. Upon irradiation of the target with neutrons from a nuclear reactor, radioactive fission products, such as molybdenum-99, are formed, and thereafter separated from the target by the introduction of an acidic solution through the port to dissolve the irradiated inner layer. The irradiation and dissolution are thus effected in the same vessel without the necessity of transferring the fissionable material and fission products to a separate chemical reactor. Subsequently, the desired isotopes are extracted and purified. Molybdenum-99 decays to technetium-99m which is a valuable medical diagnostic radioisotope. 3 claims, 1 drawing figure

No abstract available

[en] The Mo 99 is recovered from irradiated U which is present in an acid washing solution. Following the addition of a sodium sulphite solution, the Mo is precipitated by adding α-benzoinoxine and NaOH. The precipitation can be repeated several tines once the precipitate has been dissolved in an aqueous solution. In order to purify the Mo, the Mo 99 solution is brought into contact with silver-coated activated char coal, activated charcoal, and an inorganic ion exchanger. The Mo 99 concentration is above 1000 millicurie/ml. (DG)