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Separation of Yb as YbSO4 from the 176Yb target for production of 177Lu via the 176Yb(n, γ)177Yb→177Lu process

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Abstract

An effective and simple process for the separation of 177Lu from neutron-irradiated Yb targets was developed. Irradiated Yb target was dissolved in H2SO4 solution and after reduction with sodium amalgam Yb was precipitated in the form of YbSO4. From 50 mg of Yb irradiated target only 1 mg Yb remains in solution after precipitation and separation of YbSO4. The overall recovery of 177Lu is estimated at 73%. Further efficient chromatographic separation of carrier-free 177Lu from 1 mg of Yb is relatively easy and is described in several papers.

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Authors and Affiliations

  1. Institute of Nuclear Chemistry and Technology, Dorodna 16, 03-195, Warsaw, Poland

    A. Bilewicz, K. Żuchowska & B. Bartoś

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  1. A. Bilewicz
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  2. K. Żuchowska
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  3. B. Bartoś
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Correspondence to A. Bilewicz.

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Bilewicz, A., Żuchowska, K. & Bartoś, B. Separation of Yb as YbSO4 from the 176Yb target for production of 177Lu via the 176Yb(n, γ)177Yb→177Lu process. J Radioanal Nucl Chem 280, 167–169 (2009). https://doi.org/10.1007/s10967-008-7437-7

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  • DOI: https://doi.org/10.1007/s10967-008-7437-7

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