Thermoluminescent dosimetry in the Mix-D material was used to study the dosimetric characteristics of discrete sources in the form of titanium and nylon capsules, sizes 0.8 X 2.5 and 1.7 X 7 mm with an activity of 20-40 MB K. Permissible within the limits of volume subject to radiotherapy, dose field parameters and a higher dose gradient beyond the field limits as compared to 226Ra, 198Au and 192Ir were established. Manufactured 125I discrete sources meet the requirements of interstitial radiation therapy in the protracted tumor irradiation mode.
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