Background: Actinium-225 is one of the most promising radionuclides for targeted alpha therapy. Its limited availability significantly restricts clinical trials and potential applications of Ac-based radiopharmaceuticals.
Methods: In this work, we examine the possibility of Ac production from the thermal neutron flux of a nuclear reactor. For this purpose, a target consisting of 1.4 mg of Ra(NO) (T = 1600 years) and 115.5 mg of 90 % enriched, stable GdO was irradiated for 48 h in the Breazeale Nuclear Reactor with an average neutron flux of 1.7·10 cm·s. Gadolinium-157 has one of the highest thermal neutron capture cross sections of 0.25 Mb, and its neutron capture results in emission of high-energy, prompt γ-photons. Emitted γ-photons interact with Ra to produce Ra according to the Ra(γ, n)Ra reaction. Gadolinium debulking and separation of undesirable, co-produced Ac from Ra was achieved in one step by using 60 g of branched DGA resin. After Ac ingrowth from Ra (T = 14.8 d), Ac was extracted from the Ra and Ra fraction using 5 g of bDGA resin and then eluted using 5 mM HNO.
Results: Measured activity of Ac showed that 6(1) kBq or 0.16(3) μCi (1σ) of Ra was produced at the end of bombardment from 0.9 mg of Ra.
Conclusion: The developed Ac separation is a waste-free process which can be used to obtain pure Ac in a nuclear reactor.
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