Development of a dry distillation technology for the production of 131I using medium flux reactor for radiopharmaceutical applications

被引:9
作者
Ambade, R. N. [1 ]
Shinde, S. N. [1 ]
Khan, M. S. A. [1 ]
Lohar, S. P. [1 ]
Vimalnath, K. V. [1 ]
Joshi, P. V. [1 ]
Chakraborty, Sudipta [1 ]
Pillai, M. R. A. [1 ]
Dash, Ashutosh [1 ]
机构
[1] Bhabha Atom Res Ctr, Isotope Prod & Applicat Div, Mumbai 400085, Maharashtra, India
关键词
Dry distillation; Iodine-131; Neutron irradiation; Radiochemical purity; Radionuclidic purity; Tellurium dioxide; CARRIER-FREE I-131; REMNANT ABLATION; THERAPY; RADIOIODINE; SEPARATION; TOSITUMOMAB; SCINTIGRAPHY; URANIUM;
D O I
10.1007/s10967-014-3423-4
中图分类号
O65 [分析化学];
学科分类号
070302 ; 081704 ;
摘要
The present article describes the development of an indigenous technology for large scale production of I-131 based on the neutron irradiation of TeO2 target followed by the separation of I-131 using dry distillation technique. In one batch, typically 180 g of natural TeO2 was irradiated for a period of 21 days in a thermal neutron flux of similar to 5 x 10(13) n cm(-2) s(-1), which after chemical processing provided similar to 1.85 TBq (50 Ci) of I-131. The suitability of I-131 for medical application was evaluated scrupulously in order to ensure compliance with stipulated pharmacopoeia requirement.
引用
收藏
页码:451 / 467
页数:17
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