利用HFETR制备有载体^(177)Lu  被引量:4

Production of Carrier Added^(177)Lu in HFETR

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作  者:胡映江 王磊[1,2] 吴建荣 李波 罗宁[1,2] 陈云明 曾俊杰[1,2] 孙志中 贾致军[1,2] 张劲松 HU Yingjiang;WANG Lei;WU Jianrong;LI Bo;LUO Ning;CHEN Yunming;ZENG Junjie;SUN Zhizhong;JIA Zhijun;ZHANG Jinsong(Nuclear Power Institute of China,Chengdu 610213,China;Radioisotope Engineering Technology Reasearch Center of Sichuan,Chengdu 610213,China)

机构地区:[1]中国核动力研究设计院,成都610213 [2]四川省放射性同位素工程技术研究中心,成都610213

出  处:《同位素》2023年第1期83-88,I0005,共7页Journal of Isotopes

摘  要:^(177)Lu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^(177)Lu的制备具有放射化学处理简单、^(177)Lu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176 Lu,开展有载体^(177)Lu的制备研究。本研究分别辐照天然Lu和富集176 Lu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^(177)Lu比活度约为0.87 Ci/mg,177m Lu杂质含量为0.009%;富集(86.5%)176 Lu在热中子注量率为1×1014 n·cm^(-2)·s^(-1)条件下辐照28 d,生成^(177)Lu比活度约为24.9 Ci/mg,177m Lu杂质含量为0.02%;富集(86.5%)176 Lu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^(177)Lu比活度分别为25.76 Ci/mg和28.3 Ci/mg,177m Lu杂质含量分别为0.002%和0.009%。其中,辐照富集176 Lu的热实验所生成^(177)Lu的比活度和177m Lu的含量均满足行业协会标准要求:^(177)Lu比活度≥20 Ci/mg、177m Lu杂质含量≤0.07%。综上所述,利用HFETR堆辐照富集176 Lu可制备出满足标准要求的有载体^(177)Lu,未来可根据市场需求实现有载体^(177)Lu的国产化制备,促进国内^(177)Lu的核医学应用。As an ideal medical theranostic radionuclide,^(177)Lu is widely applied in many cancer diagnostics and therapies.The carrier added^(177)Lu has the advantages of simple radiochemical process and high irradiation yield.Herein,this paper conducted the research on the preparation of carrier added^(177)Lu by thermal neutron irradiation of 176 Lu in the high flux engineering test reactor(HFETR).This work irradiated natural lutetium and enriched 176 Lu.As a result,^(177)Lu with specific activity of 0.87 Ci/mg and 177m Lu 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);^(177)Lu with specific activity of 24.9 Ci/mg and 177m Lu content of 0.02%was produced by 28 days irradiation of enriched 176 Lu(86.5%)at thermal neutron flux of 1×1014 n·cm^(-2)·s^(-1);^(177)Lu with specific activity of 25.76 Ci/mg and 177m Lu content of 0.002%was produced by 5 days irradiation of enriched 176 Lu(86.5%)at thermal neutron flux of 2×1014 n·cm^(-2)·s^(-1);and^(177)Lu with specific activity of 28.3 Ci/mg and 177m Lu content of 0.009%was produced by 12 days irradiation of enriched 176 Lu(86.5%)at thermal neutron flux of 2×1014 n·cm^(-2)·s^(-1).Among them,both^(177)Lu products using enriched 176 Lu targets meet the domestic group requirements with specific activity more than 20 Ci/mg and 177m Lu/^(177)Lu less than 0.07%.Overall,carrier added^(177)Lu which can meet the standards can be prepared by irradiation of enriched 176 Lu in HFETR.It is expected to realize localized production of carrier added^(177)Lu according to market demand and promote the domestic researches in^(177)Lu nuclear medicine applications.

关 键 词:有载体^(177)Lu 富集176 Lu 制备 辐照 比活度 

分 类 号:TL923[核科学技术—核燃料循环与材料] R817[医药卫生—影像医学与核医学]

 

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