Production of Sm-153 With Very High Specific Activity for Targeted Radionuclide Therapy

Samarium-153 ((153)Sm) is a highly interesting radionuclide within the field of targeted radionuclide therapy because of its favorable decay characteristics. (153)Sm has a half-life of 1.93 d and decays into a stable daughter nuclide ((153)Eu) whereupon β(−) particles [E = 705 keV (30%), 635 keV (50%)] are emitted which are suitable for therapy. (153)Sm also emits γ photons [103 keV (28%)] allowing for SPECT imaging, which is of value in theranostics. However, the full potential of (153)Sm in nuclear medicine is currently not being exploited because of the radionuclide's limited specific activity due to its carrier added production route. In this work a new production method was developed to produce (153)Sm with higher specific activity, allowing for its potential use in targeted radionuclide therapy. (153)Sm was efficiently produced via neutron irradiation of a highly enriched (152)Sm target (98.7% enriched, σ(th) = 206 b) in the BR2 reactor at SCK CEN. Irradiated target materials were shipped to CERN-MEDICIS, where (153)Sm was isolated from the (152)Sm target via mass separation (MS) in combination with laser resonance enhanced ionization to drastically increase the specific activity. The specific activity obtained was 1.87 TBq/mg (≈ 265 times higher after the end of irradiation in BR2 + cooling). An overall mass separation efficiency of 4.5% was reached on average for all mass separations. Further radiochemical purification steps were developed at SCK CEN to recover the (153)Sm from the MS target to yield a solution ready for radiolabeling. Each step of the radiochemical process was fully analyzed and characterized for further optimization resulting in a high efficiency (overall recovery: 84%). The obtained high specific activity (HSA) (153)Sm was then used in radiolabeling experiments with different concentrations of 4-isothiocyanatobenzyl-1,4,7,10-tetraazacyclododecane tetraacetic acid (p-SCN-Bn-DOTA). Even at low concentrations of p-SCN-Bn-DOTA, radiolabeling of 0.5 MBq of HSA (153)Sm was found to be efficient. In this proof-of-concept study, we demonstrated the potential to combine neutron irradiation with mass separation to supply high specific activity (153)Sm. Using this process, (153)SmCl(3) suitable for radiolabeling, was produced with a very high specific activity allowing application of (153)Sm in targeted radionuclide therapy. Further studies to incorporate (153)Sm in radiopharmaceuticals for targeted radionuclide therapy are ongoing.