Abstract
Four production methods of 177Lu, e.g. from natural and enriched Lu and from natural and enriched Yb were considered and experimentally evaluated. The samples of all 4 materials were irradiated in a nuclear reactor, the activity of 177Lu measured and compared with a computed one. In the case of 177Lu produced from enriched Lu target the amount of activity obtained is 40 to 70% higher than calculated. The results achieved will be applied for the optimization of 177Lu production for medical applications.
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Mikolajczak, R., Parus, J.L., Pawlak, D. et al. Reactor produced 177Lu of specific activity and purity suitable for medical applications. Journal of Radioanalytical and Nuclear Chemistry 257, 53–57 (2003). https://doi.org/10.1023/A:1024784924154
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DOI: https://doi.org/10.1023/A:1024784924154