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. 利用HFETR制备有载体177Lu[J]. 同位素, 2023, 36(1): 83-88. DOI: 10.7538/tws.2021.youxian.132
引用本文: 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. 利用HFETR制备有载体177Lu[J]. 同位素, 2023, 36(1): 83-88. DOI: 10.7538/tws.2021.youxian.132
HU Yingjiang, WANG Lei, WU Jianrong, LI Bo, LUO Ning, CHEN Yunming, ZENG Junjie, SUN Zhizhong, JIA Zhijun, ZHANG Jinsong. Production of Carrier Added 177Lu in HFETR[J]. Journal of Isotopes, 2023, 36(1): 83-88. DOI: 10.7538/tws.2021.youxian.132
Citation: HU Yingjiang, WANG Lei, WU Jianrong, LI Bo, LUO Ning, CHEN Yunming, ZENG Junjie, SUN Zhizhong, JIA Zhijun, ZHANG Jinsong. Production of Carrier Added 177Lu in HFETR[J]. Journal of Isotopes, 2023, 36(1): 83-88. DOI: 10.7538/tws.2021.youxian.132

利用HFETR制备有载体177Lu

Production of Carrier Added 177Lu in HFETR

  • 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。

     

    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 enriched 176Lu 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.

     

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