نوع مقاله : مقاله پژوهشی
نویسندگان
1 پژوهشکده چرخه سوخت هسته‌ای، پژوهشگاه علوم و فنون هسته‌ای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران- ایران
2 گروه فنی و مهندسی، دانشگاه کاشان، کدپستی: 8731753153، کاشان- ایران
چکیده
پسماندهای مایع حاوی پاره‌های شکافت، منبع ارزشمندی از انواع رادیوایزوتوپ‌های کاربردی می‌باشند که با انتخاب یک روش رادیوشیمیایی مناسب می‌توان رادیوایزوتوپ مدنظر را از آن استحصال نمود. به دلیل در دسترس نبودن پسماند، در این مقاله تلاش شده است تا محلول معادل پسماند مایع نوعی تأسیسات تولید مولیبدن-99 طی شبیه‌سازی با کد MCNPX محاسبه و به صورت آزمایشگاهی با استفاده از نمک‌های موجود ساخته شود. سپس رادیوردیاب‌های مختلفی از عناصر به روش فعال‌سازی نوترونی تولید و به محلول معادل اضافه شد. بررسی‌ها نشان داد که برای ردیابی سریم در فرایند، می‌توان از تابش گامای keV 145/4 مرتبط با 141Ce تولید شده به روش فعال‌سازی استفاده نمود. مکانیزم پرتودهی و همچنین طیف‌نگاری توسط کد MCNPX شبیه‌سازی شد و نتایج با اندازه‌گیری‌های تجربی مقایسه گردد.
کلیدواژه‌ها
عنوان مقاله [English]
Simulation and determination of the appropriate radiotracer to study the behavior of cerium element in radiochemical processes
نویسندگان [English]
- A. Bahrami Samani 1
- B. Taheri 2
- I. Dehghan 2
- S. Shirvani Arani 1
1 Nuclear Fuel Cycle Research School, Nuclear Science and Technology Research Institute, AEOI, P.O.Box: 11365-8486, Tehran - Iran
2 Department of Engineering, University of Kashan, Postal Code: 8731753153, Kashan - Iran
چکیده [English]
Liquid wastes containing fission fragments are valuable sources of useful radioisotopes that can be extracted using suitable radiochemical methods. This article addresses the challenge of unavailable waste by simulating a solution equivalent to the liquid waste from a 99Mo production facility using the MCNPX code and preparing it with laboratory-available salts. Various radiotracers of elements were subsequently produced via the neutron activation method and added to the equivalent solution. Investigations focused on tracing cerium in the process, utilizing the 145.4 keV gamma radiation from 141Ce produced during activation. The irradiation mechanism and spectroscopy were simulated using the MCNPX code, and the results were compared with experimental measurements.
کلیدواژه‌ها [English]
- Radiotracer
- Neutron activation
- 141Ce
- HPGe
- MCNPX
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