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Published: 2015-03-30
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DOI: https://doi.org/10.53747/jnst.v5i1.181
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Vol. 5 No. 1 (2015)
Section
Articles
How to Cite
Nguyen , N. T., Duong , V. D., Bui , V. C., Pham , T. M., & Nguyen , T. H. (2015). Study on the production of ¹⁷⁷Lu for medical purposes at the Dalat Research Reactor. Part 1. Study on production of ¹⁷⁷Lu at the Dalat Research Reactor. Nuclear Science and Technology, 5(1), 18-25. https://doi.org/10.53747/jnst.v5i1.181

Study on the production of ¹⁷⁷Lu for medical purposes at the Dalat Research Reactor. Part 1. Study on production of ¹⁷⁷Lu at the Dalat Research Reactor

Nguyen Ngoc Tuan1, Duong Van Dong1, Bui Van Cuong1, Pham Thanh Minh1, Nguyen Thi Hang1
1 Dalat Nuclear Research Institute, No.1 Nguyen Tu Luc, Da Lat City

Main Article Content

Abstract

Lutetium-177 (177Lu) radioisotope used for medical purposes has been produced at the Dalat Nuclear Research Reactor during 2012-2014. The product was synthezed by the activation reaction 176Lu (n,γ) 177Lu. The target was Lutetium oxide with an abundance of 176Lu being 2.59% and the irradiation was conducted with a neutron flux of 2.1013 n cm-2 s-1. The activity of the 177Lu product was 39,59 Ci g-1 after 108 hous of the irradiation. The yield of this method was much higher compared to those of the reaction 176Yb(n, γ)177Yb → 177Lu + β- which for the same time could be 15mCi/50mg only. Because of low specific radioactivity the preparation of 177Lu made from the activation of 176Yb cannot be applied for the medical purposes. Additionally, the separation yield of 177Lu from 177Yb is rather low, it is usualy of approximately 70%.

Article Details

Keywords

Activation reaction, neutron flux, lutetium, abundance separation yield

References

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