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Cyclotron production of 68Ga via the 68Zn(pn)68Ga reaction in aqueous solution

机译:在水溶液中通过68Zn(pn)68Ga反应进行回旋加速器生产68Ga

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摘要

The objective of the present work is to extend the applicability of the solution target approach to the production of 68Ga using a low energy cyclotron. Since the developed method does not require solid target infrastructure, it offers a convenient alternative to 68Ge/68Ga generators for the routine production of 68Ga. A new solution target with enhanced heat exchange capacity was designed and utilized with dual foils of Al (0.20 mm) and Havar (0.038 mm) separated by helium cooling to degrade the proton energy to ~14 MeV. The water-cooled solution target insert was made of Ta and its solution holding capacity (1.6 mL) was reduced to enhance heat transfer. An isotopically enriched (99.23%) 1.7 M solution of 68Zn nitrate in 0.2 N nitric acid was utilized in a closed target system. After a 30 min irradiation at 20 μA, the target solution was unloaded to a receiving vessel and the target was rinsed with 1.6 mL water, which was combined with the target solution. An automated module was used to pass the solution through a cation-exchange column (AG-50W-X8, 200-400 mesh, hydrogen form) which efficiently trapped zinc and gallium isotopes. 68Zn was subsequently eluted with 30 mL of 0.5 N HBr formulated in 80% acetone without any measurable loss of 68Ga. 68Ga was eluted with 7 mL of 3 N HCl solution with 92-96% elution efficiency. The radionuclidic purity was determined using an HPGe detector. Additionally, ICP-MS was employed to analyze for non-radioactive metal contaminants. The product yield was 192.5 ± 11.0 MBq/μ·h decay-corrected to EOB with a total processing time of 60-80 min. The radionuclidic purity of 68Ga was found to be >99.9%, with the predominant contaminant being 67Ga. The ICP-MS analysis showed small quantities of Ga, Fe, Cu, Ni and Zn in the final product, with 68Ga specific activity of 5.20-6.27 GBq/μg. Depending upon the user requirements, 68Ga production yield can be further enhanced by increasing the 68Zn concentration in the target solution and extending the irradiation time. In summary, a simple and efficient method of 68Ga production was developed using low energy cyclotron and a solution target. The developed methodology offers a cost-effective alternative to the 68Ge/68Ga generators for the production of 68Ga.
机译:本工作的目的是将解决方案目标方法的适用性扩展到使用低能回旋加速器生产 68 Ga的方法。由于开发的方法不需要坚固的目标基础设施,因此它可以代替 68 Ge / 68 Ga发生器,用于常规生产 68 嘎。设计并使用了一种新的具有增强的热交换能力的目标靶材,并通过氦冷却将铝箔(0.20 mm)和哈瓦合金(0.038 mm)的双箔分开,从而将质子能量降低至约14 MeV。水冷溶液靶插入物由Ta制成,降低了溶液保持能力(1.6 mL)以增强热传递。在封闭的目标系统中使用同位素浓缩的(99.23%)1.7 M的 68 硝酸锌在0.2 N硝酸中的溶液。在20μA下照射30分钟后,将目标溶液卸载到接收容器中,并用1.6 mL水冲洗目标,将其与目标溶液合并。使用自动化模块使溶液通过阳离子交换柱(AG-50W-X8,200-400目,氢形式),该柱可有效捕获锌和镓同位素。随后用在80%丙酮中配制的30 mL 0.5 N HBr洗脱 68 Zn,而没有任何可测量的 68 Ga损失。用7 mL的3 N HCl溶液洗脱 68 Ga,洗脱效率为92-96%。使用HPGe检测器测定放射性核素纯度。此外,ICP-MS还用于分析非放射性金属污染物。经EOB衰减校正后的产品收率为192.5±11.0 MBq /μ·h,总处理时间为60-80分钟。发现 68 Ga的放射性核素纯度> 99.9%,主要污染物为67Ga。 ICP-MS分析表明,最终产物中少量的Ga,Fe,Cu,Ni和Zn, 68 Ga比活度为5.20-6.27 GBq /μg。根据用户要求,通过增加目标溶液中 68 Zn的浓度并延长照射时间,可以进一步提高 68 Ga的产率。总之,使用低能回旋加速器和目标解决方案,开发了一种简单高效的 68 Ga生产方法。所开发的方法为生产 68 Ga的 68 Ge / 68 Ga发生器提供了一种经济高效的替代方案。

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