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

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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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Authors and Affiliations

  1. Nuclear Engineering and Physics Department, Amir Kabir University, P.O. Box 15875-4413, Tehran, Iran

    S. Z. Islami-Rad & M. Shamsaei

  2. Nuclear Science and Technology Research Institute, AEOI, P.O. Box 14155-1339, Tehran, Iran

    S. Z. Islami-Rad, R. Gholipour-Peyvandi & M. Ghannadi-Maragheh

Authors
  1. S. Z. Islami-Rad
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  2. M. Shamsaei
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  3. R. Gholipour-Peyvandi
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  4. M. Ghannadi-Maragheh
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Correspondence to S. Z. Islami-Rad.

Additional information

Published in Russian in Radiokhimiya, 2011, Vol. 53, No. 6, pp. 542–544.

The text was submitted by the authors in English.

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Islami-Rad, S.Z., Shamsaei, M., Gholipour-Peyvandi, R. et al. Reactor production and purification of 153Sm radioisotope via natSm target irradiation. Radiochemistry 53, 642–645 (2011). https://doi.org/10.1134/S1066362211060129

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