摘要
为了获得高质量89Zr核素用于核医学显像,利用HM-20S型回旋加速器辐照89Y靶制备89Zr,对核反应激发函数进行了计算,设计了靶系统并制备靶片通过回旋加速器辐照制备89Zr,对靶片放化分离方法和89Zr标记工艺进行了研究.结果表明,回旋加速器制备89Zr最佳束流能量为 9～13.5 MeV,其中在13.5 MeV能量处获得最大反应截面.回旋加速器束流引出为 14 MeV,经真空膜和靶膜衰减后剩余能量约为12.86 MeV,束流在89Y靶中呈高斯分布,射程约为0.821 mm.89Y靶片经15µA束流辐照1.50～3.33 h,得到轰击结束时89Zr活度为 22.20～85.45 mCi,产额约为 36.51～63.30 MBq/(µA·h).采用UTEVA树脂从辐照后的靶片中分离89Zr,89Zr回收率为 86.27%,Y(Ⅲ)去除率为 99.80%.89Zr-DFO-NCS标记化合物放化纯度>98%,标记效果良好.
Abstract
In order to obtain high quality 89Zr nuclide for nuclear medicine imaging,89Zr was produced by irradiating 89Y with HM-20S cyclotron.The nuclear reaction excitation function was calculated.The target system was designed and the target was prepared.89Zr was prepared by irradiating target with cyclotron.The radiochemical separation method of the target and the 89Zr labeling process were studied.The results show that the optimum energy range of 89Zr beam produced by cyclotron was 9-13.5 MeV,while,the maximum reaction cross section was 13.5 MeV energy.The extracted beam current of the cyclotron is 14 MeV,and the residual energy is about 12.86 MeV after attenuation by the vacuum film and the target film.The beam has a Gaussian distribution in the 89Y target,and the range is approximately 0.821 mm.The activity of 89Zr at the end of bombardment was 22.20-85.45 mCi and the yield was about 36.51-63.30 MBq/(μA·h)when 89Y target was irradiated with 15 μA beam for 1.50-3.33 h.UTEVA resin was used to separate 89Zr from the irradiated target.The recovery rate of 89Zr was 86.27%,and the removal rate of Y(Ⅲ)was 99.80%.Successful 89Zr-DFO-NCS labeling was performed with a radiochemical purity of more than 98%.
基金项目
山东省重点研发计划"核动未来"科技示范工程项目(2022SFGC0501)
国家科技期刊平台
NSTL
万方数据