利用HFETR制备有载体<sup>177</sup>Lu

胡映江; 王磊; 吴建荣; 李波; 罗宁; 陈云明; 曾俊杰; 孙志中; 贾致军; 张劲松

doi:10.7538/tws.2021.youxian.132

利用HFETR制备有载体¹⁷⁷Lu

中国核动力研究设计院,成都610213
四川省放射性同位素工程技术研究中心,成都610213

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出版历程
- 刊出日期: 2023-02-19

Production of Carrier Added ¹⁷⁷Lu in HFETR

Nuclear Power Institute of China, Chengdu 610213, China
Radioisotope Engineering Technology Reasearch Center of Sichuan, Chengdu 610213, China

摘要

摘要: ¹⁷⁷Lu是一种优良的诊疗一体化医用放射性核素，其标记的放射性药物被广泛用于多种癌症的诊断和治疗。其中，有载体¹⁷⁷Lu的制备具有放射化学处理简单、¹⁷⁷Lu产量高等优点。为此，在高通量工程试验堆（HFETR）中利用热中子辐照¹⁷⁶Lu，开展有载体¹⁷⁷Lu的制备研究。本研究分别辐照天然Lu和富集¹⁷⁶Lu进行热实验验证，结果表明：天然Lu在2×10¹⁴ n·cm^-2·s^-1热中子通量下辐照13 d，生成¹⁷⁷Lu比活度约为0.87 Ci/mg，^177mLu杂质含量为0.009%；富集(86.5%)¹⁷⁶Lu在热中子注量率为1×10¹⁴ n·cm^-2·s^-1条件下辐照28 d，生成¹⁷⁷Lu比活度约为24.9 Ci/mg，^177mLu杂质含量为0.02%；富集(86.5%)176Lu在热中子注量率为2×1014 n·cm^-2·s^-1条件下辐照5 d和12 d，生成¹⁷⁷Lu比活度分别为25.76 Ci/mg和28.3 Ci/mg，^177mLu杂质含量分别为0.002%和0.009%。其中，辐照富集¹⁷⁶Lu的热实验所生成¹⁷⁷Lu的比活度和^177mLu的含量均满足行业协会标准要求：¹⁷⁷Lu比活度≥20 Ci/mg、^177mLu杂质含量≤0.07%。综上所述，利用HFETR堆辐照富集¹⁷⁶Lu可制备出满足标准要求的有载体¹⁷⁷Lu，未来可根据市场需求实现有载体¹⁷⁷Lu的国产化制备，促进国内¹⁷⁷Lu的核医学应用。
- 有载体¹⁷⁷Lu /
- 富集¹⁷⁶Lu /
- 制备 /
- 辐照 /
- 比活度
Abstract: As an ideal medical theranostic radionuclide, ¹⁷⁷Lu is widely applied in many cancer diagnostics and therapies. The carrier added 177Lu has the advantages of simple radiochemical process and high irradiation yield. Herein, this paper conducted the research on the preparation of carrier added ¹⁷⁷Lu by thermal neutron irradiation of ¹⁷⁶Lu in the high flux engineering test reactor (HFETR). This work irradiated natural lutetium and enriched ¹⁷⁶Lu. As a result, ¹⁷⁷Lu with specific activity of 0.87 Ci/mg and ^177mLu content of 0.009% was produced by 13 days irradiation of natural Lu at thermal neutron flux of 2×10¹⁴ n·cm^-2·s^-1; ¹⁷⁷Lu with specific activity of 24.9 Ci/mg and 177mLu content of 0.02% was produced by 28 days irradiation of enriched ¹⁷⁶Lu (86.5%) at thermal neutron flux of 1×10¹⁴ n·cm^-2·s^-1; ¹⁷⁷Lu with specific activity of 25.76 Ci/mg and ^177mLu content of 0.002% was produced by 5 days irradiation of enriched ¹⁷⁶Lu (86.5%) at thermal neutron flux of 2×1014 n·cm-2·s-1; and ¹⁷⁷Lu with specific activity of 28.3 Ci/mg and 177mLu content of 0.009% was produced by 12 days irradiation of enriched ¹⁷⁶Lu (86.5%) at thermal neutron flux of 2×10¹⁴ n·cm^-2·s^-1. Among them, both ¹⁷⁷Lu products using enriched¹⁷⁶Lu targets meet the domestic group requirements with specific activity more than 20 Ci/mg and ^177mLu/¹⁷⁷Lu less than 0.07%. Overall, carrier added ¹⁷⁷Lu which can meet the standards can be prepared by irradiation of enriched ¹⁷⁶Lu in HFETR. It is expected to realize localized production of carrier added ¹⁷⁷Lu according to market demand and promote the domestic researches in ¹⁷⁷Lu nuclear medicine applications.
- carrier added ¹⁷⁷Lu /
- enriched ¹⁷⁶Lu /
- preparation /
- irradiation /
- specific activity

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参考文献(7)

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