Document Type : Research Paper

Authors

• S.Z Islami Rad
• M Shamsaei
• R Gholipour Peyvandi
• M Ghannadi Maragheh
• A Bahrami Samani
• S Shirvani

Abstract

The ¹⁵³Sm production by neutron bombardment of a natural samarium target produces ^154,155,156Eu impurities. Therefore, it is important to investigate amount of impurities and their separation methods. In this study, ¹⁵³Sm was separated from Eu radioisotopes by ion exchange chromatography. Natural Sm₂O₃ powder was dissolved in HNO₃ and encapsulated in aluminum foils. The target was irradiated by the Tehran 5MW Research Reactor with the neutron flux of 5´10¹³ n cm^-2 s^-1. The irradiated target was dissolved in HCl and was injected into a chromatography column that was packed with Dowex-50Wx8, 200-400 mesh resin. As a result, ¹⁵³Sm was separated with the recovery yield ofmore than 65% with a purity better than 99.8% from Eu impurities

Highlights

 

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Keywords

• Radionuclide
• Samarium-153
• Radionuclide Purity
• Separation
• Dowex-50Wx8 Resin
• Ion Exchange Chromatography