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Short lived  α -emitting radionuclides have enormous potential to be used in the targeted therapy.  149 Tb (4.118 h) is among the few  α -emitting radionuclides which are projected for human clinical use. Therefore, direct production of  149 Tb was aimed from the  12 C induced reaction on natural praseodymium target of 15 mg∕cm 2  thickness at 71.5 MeV incident beam energy. No-carrier-added (nca)  149,150,151 Tb radionuclides were produced in the target matrix along with  149 Gd, which is also the decay product of  149 Tb, with relatively high yield of  149 Tb. An efficient radiochemical separation method was developed to separate nca  149–151 Tb from bulk praseodymium and coproduced Gd by liquid–liquid extraction (LLX) using aqueous HCl and liquid cation extracting agent di-(2-ethylhexyl)phosphoric acid (HDEHP) dissolved in cyclohexane. Quantitative extraction of nca  149–151 Tb was achieved from bulk target with a high separation factor of 4.7×10 5 .

Investigation on the production and isolation of 149,150,151 Tb from 12 C irradiated natural praseodymium target