Abstract
211At was produced in the 209Bi(4He, 2n)211At reaction. The yield was separated from the irradiated bismuth target by a simple method, based on dry distillation. The optimized conditions of the method were studied by monitoring the astatine radioactivity with gamma-ray spectrometers. The no-carrier-added 211At solutions were prepared with eluents, namely distilled water, ethanol, methanol, or chloroform. Generally, the recovery yields obtained with the utilization of 1.6 mL of the eluent were 26–75%. The prepared 211At solutions were subjected to thin-layer chromatography and high-performance liquid chromatography to identify the chemical species present.
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