Search

149Tb is currently considered to be a promising α-emitting isotope radioimmunotherapy. It is shown that it can be obtained without the use of a carrier by irradiating a target consisting of Eu2O3 with 4He with energy 63 MeV. After irradiation, radiochemical separation of terbium radioisotopes was performed in a time not exceeding the half-life of 149Tb (4.12 h). It was based on reductive co-precipitation of europium and extraction-chromatographic purification. The obtained product, including 149Tb and the associated terbium radioisotopes, were analyzed by means of alpha- and gamma-spectrometry. It was concluded that the combination and sequence of approaches used in this work allow rapid production of short-lived 149Tb and the use of the technological route implemented in this work in practice. [ABSTRACT FROM AUTHOR]

The saturation yield of the rhenium radioisotopes 186Re, 188Re, and 189Re on irradiation of a 186W target by the nuclei 4He, 3He, 1H, and 2H with energy 47, 25, 15.3, and 19 MeV, respectively, was measured by the activation method. The chosen energy of the accelerated particles made it possible to minimize the contribution of the activity of long-lived rhenium radioisotopes in the desired radionuclides. The highest yield 3240 ± 330 MBq/μA was obtained for the radioisotope 186Re in the reaction 186W(2H, 2n)186Re. The obtained yield makes it possible to plan on using in radioimmunotherapy the radionuclide 186Re produced by means of this reaction. [ABSTRACT FROM AUTHOR]

The concept of a cascade gas target with krypton isotopes for medical 82Sr radioisotope production is described. Using this concept, an experimental setup was created at the U-150 cyclotron of the Kurchatov Institute NRC for 82Sr production with an 82Sr yield of approximately 53 μCi/μA h using the 80Kr(4He, 2n)82Sr reaction in the 80Kr target module. Descriptions of the system and its operation are presented. The setup performed well with reproducible results. It is noted that the 82Sr radioisotope produced using the setup is free from an admixture of the 85Sr radioisotope that is responsible for approximately one-half the irradiation dose to workers using standard 82Sr–82Rb isotope generators. [ABSTRACT FROM AUTHOR]

The formation of radiation defect clusters as interstitial dislocation loops in pyrographite irradiated by 20-MeV carbon ions in a cyclotron has been studied by means of synchrotron radiation scattering. The experimental data are interpreted in terms of the Krivoglaz model and the model of deformation domain formation by dislocation loops. Parameters of the pyrographite crystal lattice in the deformed state upon ion irradiation have been determined using experimental data on the shift and broadening of the Bragg peaks. The results of experiments and their theoretical analysis indicate that the phenomena of the crystal lattice densification (shrinkage) and the radiation-induced swelling (increase in volume) observed for graphite irradiated by fast neutrons in a nuclear reactor can be studied in model experiments on charged particle accelerators using irradiation of the samples with carbon ions at much lower doses and significantly shorter exposure times. [ABSTRACT FROM AUTHOR]