Reactor production and purification of 153Sm radioisotope via natSm target irradiation

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%.