Reactor Production and Purification of ~(153)Sm Radioisotope via ~(nat)Sm Target Irradiation

摘要

Neutron irradiation of a natural Sm target is performed to produce ~(153)Sm. Ion-exchange chromatography is used to separate ~(153)Sm from Eu radionuclides produced in the process. To prepare a target, Sm_(2)O_(3) powder is dissolved in 0.2 ml of HNO_(3) in a quartz vial. Samarium is deposited onto the vial walls by passing nitrogen gas at 120 deg C. The prepared samarium target is encapsulated in aluminum foil and irradiated in a 5-MW reactor in 5 X 10~(13) 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 ~(153)Sm is separated from Eu radionuclides with ~(153)Sm recovery yield of more than 66percent and purity better than 99.8percent.