Abstract
Neutron irradiation of a natural Sm target is performed to produce 153Sm. Ion-exchange chromatography is used to separate 153Sm from Eu radionuclides produced in the process. To prepare a target, Sm2O3 powder is dissolved in 0.2 ml of HNO3 in a quartz vial. Samarium is deposited onto the vial walls by passing nitrogen gas at 120°C. The prepared samarium target is encapsulated in aluminum foil and irradiated in a 5-MW reactor in 5 × 1013 n cm−2 s−1 flux. The irradiated target is dissolved in 1 M HCl, and the produced radioisotopes are determined with an HPGe nuclear detector. Finally 153Sm is separated from Eu radionuclides with 153Sm recovery yield of more than 66% and purity better than 99.8%.
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