مجله علوم، مهندسی و فناوری هسته‌ای

ارزیابی خلوص رادیونوکلئیدی رنیوم-186 و 188 تولید شده از پرتودهی رنیوم طبیعی

نوع مقاله : مقاله پژوهشی

نویسندگان

زهرا پورحبیب 1
حسن رنجبر 2
علی بهرامی سامانی 2
علی‌اصغر شکری 1

1 دانشکده فیزیک، دانشگاه پیام نور، صندوق پستی: 4697-19395، تهران- ایران

2 پژوهشکده چرخه سوخت هسته‌ای، پژوهشگاه علوم و فنون هسته‌ای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران

https://doi.org/10.24200/nst.2020.1140
چکیده
امروزه استفاده از رادیونوکلئیدهای رنیوم-186 و 188 در تولید رادیوداروهای مختلف رشد چشم­گیری داشته است. این دو رادیونوکلئید دارای ویژگی‌­های مناسبی نظیر گسیل ذارات بتا با برد و انرژی مناسب و تابش پرتوی گامای مناسب برای تصویربرداری و ارزیابی توزیع زیستی جهت درمان سرطان هستند. با توجه به انرژی و برد این رادیونوکلئید­ها، رنیوم-186 با برد کم برای درمان تومور­های کوچک و رنیوم-188 با برد بیش‌تر در نابودی تومور­های بزرگ مناسب هستند. در این پژوهش فرایند تولید هم‌­زمان این دو رادیونوکلئید از طریق پرتودهی رنیوم طبیعی برای تولید رادیوداروی ترکیبی جهت درمان تومور­های با اندازه­‌های مختلف مورد بررسی قرار گرفته است. در مطالعه‌­ی حاضر، پرتودهی mg 1 رنیوم طبیعی در شار نوترونی 1.s2-cm 1013×3 به مدت 7 روز مورد ارزیابی قرار گرفت و اکتیویته‌­ی محصولات اصلی محاسبه گردید. از آن­‌جایی که وجود ناخالصی‌ها دز نامطلوب و اضافی به بیمار تحول می‌دهد، حضور و میزان اکتیویته‌­ی این رادیونوکلئیدها مورد بررسی قرار گرفته است. نتایج نشان می‌­دهند که از طریق پرتودهی رنیوم طبیعی، رادیونوکلئیدهای رنیوم-186 و 188 را می‌­توان به ­طور هم‌­زمان با میزان اکتیویته‌­ی مناسب جهت تولید رادیوداروی ترکیبی تولید کرد. هم‌چنین محاسبات نظری نشان می‌­دهد میزان ناخالصی‌­های تولیدی در مقایسه با محصولات اصلی، بسیار ناچیز هستند.

کلیدواژه‌ها

تولید رادیونوکلئید
رنیوم-186
رنیوم-188
خلوص رادیونوکلئیدی

عنوان مقاله English

Evaluation of radionuclidic purity of Re-186 and Re-188 produced by irradiation of natural Rhenium

نویسندگان English

Z. Pourhabib 1
H. Ranjbar 2
A. Bahrami Samani 2
A.A. Shokri 1
1 Department of Physics, Payame Noor University, P.O. Box: 19395-4697, Tehran-Iran
2 Materials and Nuclear Fuel Research School, Nuclear Science and Technology Research InstiNuclear Fuel Cycle Research School, Nuclear Science and Technology Research Institute, AEOI, P.O.Box: 11365-8486, Tehran – Irantute, AEOI,
چکیده English

These days, the use of Rhenium 186 and 188 radionuclides in the production of various radiopharmaceuticals has grown considerably. These two radionuclides have good features such as emitting beta particles with appropriate range and energy, and gamma rays for imaging and evaluating biological distribution in cancer treatment. Regarding the energy and range of these radionuclides, Rhenium 186 with small range is suitable for treating small tumors; and Rhenium 188 with greater range is appropriate to destroy large tumors. In this study, the simultaneous production of these two radionuclides by natural rhenium irradiation for the production of a combined radiopharmaceutical, to treat tumors with various sizes has been investigated. For the purpose of this study, the irradiation of 1 mg of natural rhenium in a neutron flux of 3×1013 cm-2s-1 for 7 days was evaluated and the activity of the main products was calculated. Since the presence of impurities delivers an unwanted and excess dose to the patient, the presence and activity level of these radionuclides have also been studied. The results of the study showed that by the irradiation of natural rhenium, Rhenium 186 and 188 radionuclides can be produced simultaneously with the appropriate activity level for using the combination of both radionuclides. Also, theoretical calculations showed that the amount of produced impurities compared to the original products is negligible.

کلیدواژه‌ها English

Radioisotope production
Rhenium186
Rhenium188
Radionuclidic purity
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