基于质子加速器液体靶制备44gSc的工艺研究

Optimization of 44gSc Production Using Cyclotron-irradiated Liquid Target

  • 摘要: 正电子核素钪-44(44gSc)因其理想的核素性质,在肿瘤诊断领域具有潜在的应用前景。为解决44gSc供应短缺问题,开发基于质子回旋加速器液体靶的新型制备方法,利用硝酸钙靶制备44gSc。通过数值模拟相关核反应的激发函数,计算了钪放射性同位素的生成情况及44gSc的核纯度随时间变化规律。结果表明采用天然钙靶制备44gSc的核纯度最高为95.8%,且存在43Sc、44mSc、47Sc和48Sc等副产物。利用14.5 MeV质子束辐照了天然硝酸钙液体靶,实测辐照结束(EOB)时44gSc的产率为2.5 MBq/μAh,较文献报道的结果提高了3.4倍,辐照后核纯度为95.8%±1.0%,与模拟结果一致。通过支链型DGA树脂分离钙离子和钪离子,钪离子的回收率为97.0%。利用自制44gSc开展了小鼠PET成像实验,结果显示,静脉注射0.33 MBq 44gScScCl3后,心脏血池区域呈现显著放射性浓聚,成像清晰,初步表明了44gSc在PET成像中的应用潜力。

     

    Abstract: The positron-emitting radionuclide scandium-44 (44gSc) demonstrates significant potential in tumor diagnosis due to its optimal decay properties (T1/2=4.04 h, E_\mathrmavg,\textβ^+ =632.0 keV, branching ratio (BR)=94.3%). However, its limited availability has constrained the development of related radiopharmaceuticals. To address this supply limitation, the production of 44gSc via the reaction 44Ca(p,n)44gSc using a medical cyclotron was reported. Numerical simulations were employed to optimize irradiation parameters for maximizing production yield and radionuclidic purity. Subsequently, proton irradiation of a natural-abundance Ca liquid target was utilized to produce 44gSc, and the PET imaging performance of 44gSc was also investigated. To calculate theoretical yield and radionuclidic purity, excitation functions were simulated using TALYS 2.0, ALICE-IPPE, and EMPIRE 3.2 nuclear reaction codes. Based on these calculations, liquid targets containing high-concentration (168 mg/mL) calcium nitrate were irradiated using a GE PETtrace cyclotron. The proton beam was delivered at 14.5 MeV with 7-10 μA intensity for 30-90 min irradiation. After irradiation, the targets were processed through branched DGA resin chromatography for radiochemical purification. Radionuclidic, radiochemical, and chemical purity were assessed using an HPGe detector, TLC scanner, and ICP-OES, respectively. The resulting 44gScScCl3 samples (0.33 MBq injection dose) were evaluated through PET imaging studies in murine models to assess their in vivo performance. Numerical simulations demonstrate that 14.5 MeV is the optimal proton energy for the 44Ca(p,n)44gSc reaction, achieving a theoretical radionuclidic purity of 95.8% at the end-of-bombardment (EOB). The primary impurities consist of 43Sc (2.1%), 44mSc (0.6%), 47Sc (0.2%) and 48Sc (1.3%). The experimental results show that compared to other tested conditions, the 10 μA beam intensity with 50 min of irradiation delivers a higher yield. The production yield at EOB is 2.5 MBq/μAh for 44gSc, representing a 3.4-fold improvement over existing data, and the maximum EOB activity is 20.6 MBq. Chemical purification of Sc3+ achieves a recovery yield of 97.0%, which is comparable to literature values. The radiochemical purity exceeds 99% as verified by TLC. ICP-OES analysis confirms effective removal of metallic contaminants, retaining only 362.4 ppm Ca while maintaining other metal impurities (Zn, Fe, Al, Mn) below 4 ppm. Radiolabeling studies show that Ca2+ exhibits negligible influence on labeling yield. Gamma spectroscopy measurements confirm an EOB radionuclidic purity of 95.8%±1.0%, consistent with simulations. Preliminary PET imaging studies reveal that 44gSc exhibits high radioactivity levels in the cardiac blood pool, indicating strong binding affinity of free Sc3+ to plasma proteins. The PET imaging of 44gSc achieves high quality even at low doses, supporting its potential for medical diagnostic applications.

     

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