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The 82Sr/82Rb generator is used to produce a radiopharmaceutical rubidium-82 chloride in saline solution for PET imaging. In this work, we studied the effect of the amount of stable strontium and calcium delivered to the sorbent (on the basis of hydrated tin dioxide) on the maximum volume of radiopharmaceutical solution that can be obtained from the generator. Sr and Ca may be delivered to the sorbent from the initial solution of strontium-82 chloride or from the eluent (0.9% NaCl) during medical application of the generator. It is shown that this volume depends on the value CSr + 0.11CCa, where CSr and CCa are molar concentrations of the elements in 1 g of the sorbent. The obtained results make it possible to increase significantly the productivity and reliability of the used generators. [ABSTRACT FROM AUTHOR]

Various methods have been developed for the extraction of a promising medical radionuclide 117mSn from proton-irradiated TiSb intermetallic compound, a target material suitable for irradiation with an intense beam of accelerated protons. To separate radiotin from Ti, Sb, and radionuclides of other elements, methods of ion-exchange chromatography and liquid extraction were used, in particular, the anion-exchange separation of tin and titanium in the form of a peroxide complex in HCl solution, extraction of tin with benzene from iodide solutions, and chromatographic purification on silica gel from citrate solutions. As a result, 117mSn of high purity, which meets the requirements for nuclear medicine, was obtained. [ABSTRACT FROM AUTHOR]

The ability of inorganic hydroxide sorbents Termoxid-5 (T-5) and Termoxid-39 (T-39) heat-treated at temperatures from 100 to 950°C to take up radionuclides of the 225Ac subfamily was examined in a wide range of solution acidities and salt compositions. T-5 and T-39 are principally suitable for the development of both direct and inverse 225Ac/213Bi generators with the activity of hundreds of millicuries of 225Ac. [ABSTRACT FROM AUTHOR]

A method for production of no-carrier-added 117mSn (NCA 117mSn) has been developed. It includes proton irradiation of thick antimony targets and chemical recovery of 117mSn by extraction of Sb with dibutyl ether and chromatographic purification on silica gel column. The method provides production of curie amounts of 117mSn with specific activity about 1000 Ci/g and high radionuclidic purity. [ABSTRACT FROM AUTHOR]

High specific activity64Cu is a radionuclide of increasing interest for PET imaging, as well as systemic and targeted radioimmunotherapy of tumours. The cross sections for production of64Cu from Zn target of natural isotopic composition were measured in the proton energy range from 141 down to 31 MeV. The stacked-foil technique was used at 160 MeV intersection point of INR proton-LINAC in Troitsk, Russia. Several Ga, Zn, Cu, Ni, Co, V and Mn RNs were detected in Zn targets at the EOB. The activity of no-carrier-added64Cu was measured through its only gamma-emission of 1346 keV (0.47% intensity). To this purpose, it was necessary to carry out a selective radiochemical separation of Ga RNs from the bulk of irradiated Zn target and other RNs. Theoretical calculations of cross sections were carried out with the CEF model and HMS-ALICE hybrid model codes and are compared with the experimental values. [ABSTRACT FROM AUTHOR]

We present a review of reactor and accelerator centers in Russia that produce medical isotopes, the majority of which are exported. In the near future, we anticipate increased isotope production for use in nuclear medicine in Russia. The existing linear accelerator at the Institute for Nuclear Research (Moscow-Troitsk) and several prospective installations are considered to be particularly capable of providing mass production of radionuclides that can substitute, to a certain extent, for the traditional medical isotopes., (© 2013 Published by Elsevier Ltd.)