Abstract: Disclosed is a method for preparing a strontium-82/rubidium-82 generator. The method includes: filling a column volume with a sorbent made of hydrated tin (IV) oxide; passing through the column an initial solution with strontium-82 radionuclide, which also contains ions of stable isotopes of calcium and strontium; and washing out rubidium-82 with a saline solution of 0.9% sodium chloride. In order to achieve a breakthrough of strontium-82 or strontium-85 below permissible levels, 0.01 and 0.1 kBq per 1 MBq 82Rb, respectively, when passing not less than 17 liters of saline solution through columns with a volume of not less than 1.6 cm3 and a dry sorbent weight of not less than 3.8 g, a specific activity of strontium-82 in the initial solution is not less than 90 GBq (2400 mCi) per mg of stable strontium cations for a generator with an activity of 3700 MBq (100 mCi).

Abstract: The invention relates to the field of nuclear technology and radiochemistry, more specifically to the production and isolation of radionuclides for medical purposes. The method for producing actinium-225 and isotopes of radium comprises irradiating a solid block of metallic thorium of a thickness of 2 to 30 mm, which is contained within a hermetically sealed casing made of a material which does not react with thorium, with a flow of accelerated charged particles with high intensity. The irradiated metallic thorium is removed from the casing and is either heated with the addition of lanthanum and the distillation of radium or is dissolved in nitric acid with the recovery of actinium-225 by extraction. A target for implementing this method consists of blocks of metallic thorium of a thickness of 2 to 30 mm, which are contained within a hermetically scaled casing made of different materials which do not react with thorium.

Abstract: The invention relates to the production of radiostrontium. The problem to be solved by the invention is the extraction of radiostrontium from a large pool of liquid metallic rubidium to improve the efficiency of radiostrontium production and simplify the technology. Sorption is carried out directly on the inner surface of the target shell at a temperature of 275 to 350° C., or by means of extraction of radiostrontium from circulating rubidium via sorption on the heated surface of a trap at a temperature of 220 to 350° C., or by means of filtering liquid rubidium through a filtering unit made of a porous material resistant to liquid rubidium metal.

Abstract: One embodiment of the present invention includes a process for production and recovery of no-carrier-added radioactive tin (NCA radiotin). An antimony target can be irradiated with a beam of accelerated particles forming NCA radiotin, followed by separation of the NCA radiotin from the irradiated target. The target is metallic Sb in a hermetically sealed shell. The shell can be graphite, molybdenum, or stainless steel. The irradiated target can be removed from the shell by chemical or mechanical means, and dissolved in an acidic solution. Sb can be removed from the dissolved irradiated target by extraction. NCA radiotin can be separated from the remaining Sb and other impurities using chromatography on silica gel sorbent. NCA tin-117m can be obtained from this process. NCA tin-117m can be used for labeling organic compounds and biological objects to be applied in medicine for imaging and therapy of various diseases.

Abstract: The invention relates to the field of nuclear technology and radiochemistry, more specifically to the production and isolation of radionuclides for medical purposes. The method for producing actinium-225 and isotopes of radium comprises irradiating a solid block of metallic thorium of a thickness of 2 to 30 mm, which is contained within a hermetically sealed casing made of a material which does not react with thorium, with a flow of accelerated charged particles with high intensity. The irradiated metallic thorium is removed from the casing and is either heated with the addition of lanthanum and the distillation of radium or is dissolved in nitric acid with the recovery of actinium-225 by extraction. A target for implementing this method consists of blocks of metallic thorium of a thickness of 2 to 30 mm, which are contained within a hermetically scaled casing made of different materials which do not react with thorium.

Abstract: One embodiment of the present invention includes a process for production and recovery of no-carrier-added radioactive tin (NCA radiotin). An antimony target can be irradiated with a beam of accelerated particles forming NCA radiotin, followed by separation of the NCA radiotin from the irradiated target. The target is metallic Sb in a hermetically sealed shell. The shell can be graphite, molybdenum, or stainless steel. The irradiated target can be removed from the shell by chemical or mechanical means, and dissolved in an acidic solution. Sb can be removed from the dissolved irradiated target by extraction. NCA radiotin can be separated from the remaining Sb and other impurities using chromatography on silica gel sorbent. NCA tin-117m can be obtained from this process. NCA tin-117m can be used for labeling organic compounds and biological objects to be applied in medicine for imaging and therapy of various diseases.

Abstract: The invention relates to producing radiostrontium. The aim of the invention is to release radiostrontium from a large mass of liquid metal rubidium, thereby making it possible to increase the efficiency of radiostrontium production and simplify the production process. Sorption is carried out directly on the inner shell of a target at a temperature of 275-350° C., or by extracting radiostrontium from circulating rubidium by sorption on the heated surface of a trap at a temperature of 220-350° C., or by filtering liquid rubidium through a filtering element made of a porous material resistant to liquid rubidium.

Abstract: A process for the production of radiostrontium consists in that a target of metallic rubidium is bombarded by a flow of accelerating charged particles. The target of irradiated rubidium is melted, whereas the extraction of radiostrontium is carried out by sorption on the surface of a sorbing material immersed into the irradiated molten metallic rubidium. As the sorbing material, use is made of materials selected from the group consisting of heat-resistant metals or metallic oxides or silicon which are inert with respect to rubidium. The resultant radiostrontium is extracted from the irradiated rubidium. The temperature of the sorbing material is selected to be close to the optimum one for the sorption of radiostrontium which is within the range of from the melting point of metallic rubidium to 220.degree. C. And the temperature of molten rubidium is selected to be close to the optimum one for the desorption of radiostrontium within the range of from 220.degree. C. to 270.degree. C.