Capability assessment of production of n.c.a. isotope 177Lu on the average flux reactor IRT-T

Abstract The article discusses the possibility of producing 177 Lu nuclide at IRT-T mid-flow research nuclear reactor. paper presents possible reactions on thermal neutrons with lutetium and ytterbium nuclei, basis which a theoretical calculation activity Lu, Yb 175 was carried out taking into account burnup over entire energy spectrum central channel TsK-1 reactor IRT-T. obtained calculations were verified experimentally by irradiation enriched targets. It is shown that upon an target mass 10 mg. within 3 weeks, 23.05 GBq, while 2.55 GBq. Two Yb2O3 samples masses 3.4 4.7 mg in 176 to 99.59% irradiated under different conditions. first sample (4.7 mg) power 100 kW for 60 minutes 497.42 MBq, 97.95 MBq. second 20 hours 6 MW 177Lu 0.805, = 0.155 Comparison calculated data experimental results showed convergence less than 20%. performed experiments make it preliminary assessment can be during production isotope reactor, as well calculate necessary radiation protection required working radioactive lutetium.