Recovery of (177)Lu from Irradiated HfO(2) Targets for Nuclear Medicine Purposes

A new method of production of one of the most widely used isotopes in nuclear medicine, (177)Lu, with high chemical purity was developed; this method includes irradiation of the HfO(2) target with bremsstrahlung photons. The irradiated target was dissolved in HF and then diluted and placed onto a column filled with LN resin. Quantitative sorption of (177)Lu could be observed during this process. The column later was rinsed with the mixture of 0.1 M HF and 1 M HNO(3) and then 2 M HNO(3) to remove impurities. Quantitative desorption of (177)Lu was achieved by using 6 M HNO(3). The developed method of (177)Lu production ensures high purification of this isotope from macroquantities of hafnium and zirconium and radioactive impurities of carrier-free yttrium. The content of (177m)Lu in (177)Lu in photonuclear production was determined. Due to high chemical and radionuclide purity, (177)Lu obtained by the developed method can be used in nuclear medicine.