用低能质子生产基于回旋加速器的镓-68:初步目标设计和回旋加速器屏蔽考虑

Luis Salas-Tapia, Tianjiao Zhang
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引用次数: 0

摘要

利用核反应堆、回旋加速器和发电机生产核医学放射性核素。基于镓-68的放射性药物在正电子发射断层扫描(PET)中得到了广泛的实验和临床应用。目前Ga-68主要是通过68Ge/68Ga发生器生产的,价格昂贵。另一种方法是利用高富集锌-68通过68Zn(p,n)68Ga反应进行回旋加速器。利用能量在(13-14)MeV或更高的质子束撞击固体靶,已经进行了生产Ga-68的研究。这项工作的主要兴趣是利用较低范围内的能量产生Ga-68,因此Ga-68可以通过较低能量的回旋加速器进入位置。本文介绍了一种利用低能质子获得Ga-68的新型靶设计方法。还考虑了适当的屏蔽以避免回旋加速器外的额外剂量。蒙特卡罗代码FLUKA用于模拟辐射与物质相互作用的过程和放射性同位素的产生。当束流能量为11 MeV,靶电流为40 μA时,模拟产生的活度约为69.1 GBq。结果表明,利用低能量质子和自屏蔽系统制备Ga-68的可行性保证了回旋加速器外的调节剂量暴露。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Production of Cyclotron-Based Gallium-68 With Low Energy Protons: Preliminary Target Design and Cyclotron Shielding Considerations
Nuclear reactors, cyclotrons and generators are being used to produce nuclear medicine radionuclides. Radiopharmaceuticals based on Gallium-68 are widely used both experimentally and clinically in Positron Emission Tomography (PET). Currently Ga-68 is mainly produced via 68Ge/68Ga generators, which are expensive. An alternative method is by cyclotron using high enriched Zinc-68 via the 68Zn(p,n)68Ga reaction. Investigations have been conducted for producing Ga-68 using a solid target impacted with a proton beam in energies between (13–14) MeV or higher. The main interest of this work is to produce Ga-68 using energies within a lower range, therefore Ga-68 can be accessed to locations with cyclotrons of lower energy. In this article, an approach to a novel target design to get Ga-68 with low energy protons is conducted. Adequate shielding to avoid extra doses outer the cyclotron is also considered. Monte Carlo code FLUKA is used to simulate the processes of interaction of radiation with matter and the radioactive isotope production. For a beam energy of 11 MeV and current on target of 40 μA the simulated produced activity is about 69.1 GBq. The results show the feasibility of producing Ga-68 with low energy protons and self-shielding system guarantees the regulation-based dose exposition outer the cyclotron.
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