Van de Voorde Michiel, Duchemin Charlotte, Heinke Reinhard, Lambert Laura, Chevallay Eric, Schneider Thomas, Van Stenis Miranda, Cocolios Thomas Elias, Cardinaels Thomas, Ponsard Bernard, Ooms Maarten, Stora Thierry, Burgoyne Andrew R
Belgian Nuclear Research Center, Institute for Nuclear Materials Science, Mol, Belgium.
Department of Physics and Astronomy, Institute for Nuclear and Radiation Physics, KU Leuven, Leuven, Belgium.
Front Med (Lausanne). 2021 Jul 19;8:675221. doi: 10.3389/fmed.2021.675221. eCollection 2021.
Samarium-153 (Sm) is a highly interesting radionuclide within the field of targeted radionuclide therapy because of its favorable decay characteristics. Sm has a half-life of 1.93 d and decays into a stable daughter nuclide (Eu) whereupon β particles [E = 705 keV (30%), 635 keV (50%)] are emitted which are suitable for therapy. Sm also emits γ photons [103 keV (28%)] allowing for SPECT imaging, which is of value in theranostics. However, the full potential of 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 Sm with higher specific activity, allowing for its potential use in targeted radionuclide therapy. Sm was efficiently produced via neutron irradiation of a highly enriched Sm target (98.7% enriched, σ = 206 b) in the BR2 reactor at SCK CEN. Irradiated target materials were shipped to CERN-MEDICIS, where Sm was isolated from the 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 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) Sm was then used in radiolabeling experiments with different concentrations of 4-isothiocyanatobenzyl-1,4,7,10-tetraazacyclododecane tetraacetic acid (-SCN-Bn-DOTA). Even at low concentrations of -SCN-Bn-DOTA, radiolabeling of 0.5 MBq of HSA 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 Sm. Using this process, SmCl suitable for radiolabeling, was produced with a very high specific activity allowing application of Sm in targeted radionuclide therapy. Further studies to incorporate Sm in radiopharmaceuticals for targeted radionuclide therapy are ongoing.
钐 - 153(Sm)因其良好的衰变特性,在靶向放射性核素治疗领域是一种极具吸引力的放射性核素。Sm的半衰期为1.93天,衰变生成稳定的子核素(Eu),同时发射出适合治疗的β粒子[能量 = 705 keV(30%),635 keV(50%)]。Sm还发射γ光子[103 keV(28%)],可用于单光子发射计算机断层显像(SPECT)成像,这在诊疗一体化中具有重要价值。然而,由于通过添加载体的生产路线导致该放射性核素的比活度有限,Sm在核医学中的全部潜力目前尚未得到充分利用。在这项工作中,开发了一种新的生产方法来生产具有更高比活度的Sm,使其有可能用于靶向放射性核素治疗。通过在SCK CEN的BR2反应堆中对高富集度的Sm靶(富集度为98.7%,σ = 206 b)进行中子辐照,有效地生产出了Sm。辐照后的靶材料被运至欧洲核子研究中心的MEDICIS,在那里通过质量分离(MS)结合激光共振增强电离从Sm靶中分离出Sm,从而大幅提高比活度。获得的比活度为1.87 TBq/mg(在BR2辐照结束并冷却后约高265倍)。所有质量分离的平均总质量分离效率达到了4.5%。SCK CEN还开发了进一步的放射化学纯化步骤,从MS靶中回收Sm,以得到可供放射性标记的溶液。对放射化学过程的每一步都进行了全面分析和表征,以进一步优化,从而实现了高效率(总回收率:84%)。然后将获得的高比活度(HSA)Sm用于不同浓度的4 - 异硫氰酸苄基 - 1,4,7,10 - 四氮杂环十二烷四乙酸(-SCN - Bn - DOTA)的放射性标记实验。即使在 -SCN - Bn - DOTA浓度较低时,也发现0.5 MBq的HSA Sm的放射性标记是有效的。在这项概念验证研究中,我们展示了将中子辐照与质量分离相结合以提供高比活度Sm的潜力。通过这个过程,生产出了具有非常高比活度、适合放射性标记的SmCl,使得Sm能够应用于靶向放射性核素治疗。目前正在进行进一步的研究,以将Sm纳入用于靶向放射性核素治疗的放射性药物中。