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On the practical aspects of large-scale production of 177Lu for peptide receptor radionuclide therapy using direct neutron activation of 176Lu in a medium flux research reactor: the Indian experience

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Abstract

This paper accentuates on the practical aspects and intricate technicalities involved in the large-scale production of 177Lu with specific activity >740 GBq mg−1 following (n,γ)177Lu route in a medium flux (~1.2 × 1014 n cm−2 s−1 thermal neutron) research reactor. The implication of target burn-up on the specific activity of 177Lu during irradiation was discussed in detail. 177Lu obtained from this route has been extensively utilized for targeted therapy in patients with neuroendocrine tumor in India. The important details available from our experience, as well as technical know-how, would be of considerable value for institutions planning to pursue 177Lu production through (n,γ)177Lu route.

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Acknowledgments

Research at the Bhabha Atomic Research Centre is part of the ongoing activities of the Department of Atomic Energy, India and is fully supported by government funding. The authors are grateful to Dr. M. R. A. Pillai, former Head, Radiopharmaceuticals Division, for his guidance, encouragement and support. The authors express their sincere thanks to Dr. Gursharan Singh, Associate Director (I), RC&I Group, BARC for his support. The authors also gratefully acknowledge Dr. S. V. Thakare and Mr. K. C. Jagadeesan, Isotope applications and Radiopharmaceuticals Division, Bhabha Atomic Research Centre for their support in arranging the irradiation of lutetium targets.

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The authors declare that they have no conflict of interests, financial, scientific or otherwise with other people or organizations in the publication of this article.

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Correspondence to Ashutosh Dash.

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Chakraborty, S., Vimalnath, K.V., Lohar, S.P. et al. On the practical aspects of large-scale production of 177Lu for peptide receptor radionuclide therapy using direct neutron activation of 176Lu in a medium flux research reactor: the Indian experience. J Radioanal Nucl Chem 302, 233–243 (2014). https://doi.org/10.1007/s10967-014-3169-z

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  • DOI: https://doi.org/10.1007/s10967-014-3169-z

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