Two methods of Lu-177 production are reviewed: irradiation of isotopically enriched Lu- 176 (direct way) and irradiation of ytterbium enriched with Yb-176 (indirect way). Based on neutronphysical calculations Lu-177 yield and specific activity were estimated for both methods. Lu-177 specific activity strongly depends on neutron flux density in the direct way, that is 75,000 Ci/g for 10- days irradiation in a neutron flux of 2.10(15) cm(-2) s(-1), and only 13,000 Ci/g after 30 days irradiation at neutron flux 1.10(14) cm(-2) s(-1). Irradiation of Yb-176 provides Lu-177 specific activity close to theoretical value (110,000 Ci/g). Neutron flux density effect Lu-177 yield, that is 530 Ci/g for 2.1015 cm(-2) s(-1) neutron flux density after 30 days irradiation. A procedure of isolation and purification of Lu-177 from irradiated targets is described based on combination of galvanostatic extraction of ytterbium followed by cation-exchange chromatography from alfa-hydroxyisobutirate solutions on BioRad AG(®)50W-X8 resin.

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Two technologies of 89 Sr production: "traditional", based on 88 Sr(n,y)-reaction, and alternative, based on 89 Y(n,p) reaction, has been discussed in the paper. The quality and suitability for radiopharmaceuticals production of two types of product (with carrier and no-carrier-added) are discussed.For more then 20 years strontium-89 is used for palliative treatment of bone metastases. Several years ago -Metastron -strontium chloride solution produced by Amersham was approved for clinical use.Two ways of strontium-89 production are known. First is «traditional» one, based on 88 Sr(n,y) 89 Sr reaction, taking place in thermal neutron fluxes. The second way is an alternative, based on 89 Y(n,p) 89 Sr reaction, occurring in fast neutron fluxes. In both cases production of strontium-89 is accompanied by radioactive impurities production, particularly -strontium-85 and strontium-90, effecting final product quality.Regardless of production technology, strontium-89 preparation should confirm a number of requirements, conditioned by its application as radiopharmatheutical. Its specific activity should be not less then 100 mCi/g, gamma-emitting impurities content should be not greater then 0,4%, strontium-90 impurity content should be not higher then 2 10" 4 %.Basic elements of technology flow-sheets, using both production ways, designed and applied by RIAR for strontium-89 production, are discussed in the report.

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