مجله سنجش و ایمنی پرتو

مجله سنجش و ایمنی پرتو

بررسی اثربخشی حفاظتی کامپوزیت پلی‌وینیل الکل-کاربید بور برای چشمه نوترونی 241Am-Be

نوع مقاله : مقاله پژوهشی

نویسندگان
پژوهشکده کاربرد پرتوها، پژوهشگاه علوم و فنون هسته‌ای، کرج، البرز، ایران
10.22052/rsm.2026.257790.1153
چکیده
کامپوزیت‌های پلیمری به خاطر سبکی، سهولت در فرآوری، دارا بودن اتم‌های هیدروژن فراوان و در نتیجه پراکندگی الاستیک با ذرات نوترون، گزینه ایده‌آلی به منظور کندسازی و حفاظ سازی نوترونی قلمداد می‌شوند. در این کار تجربی کامپوزیت پلی وینیل الکل-کاربید بور (PVA-B4C) حاوی 5 درصد وزنی از ذرات پُرکننده کاربید بور به کمک روش محلولی در ضخامت mm 061/1 ساخته شد. سایز ذرات B4C استفاده شده در این کامپوزیت بین μm 50-20 قرار داشت. سپس، کامپوزیت مذکور تحت پرتودهی چشمه نوترونی Am-Be241 با متوسط انرژی MeV 5 و اکتیویته Ci 5 قرار گرفت. به منظور اندازه‌گیری آهنگ دز نوترون‌ها در فاصله cm 100 از چشمه، از آشکارساز کروی He3 بهره‌گیری شد. نتایج اندازه‌گیری نشان داد که مقدار سطح مقطع ماکروسکوپیک کلی کامپوزیت مذکور برابر cm-1 208/0 بوده که با مقدار شبیه سازی از کد MCNP، 1.8% اختلاف دارد؛ لذا استفاده از این کامپوزیت به منظور جایگزینی حفاظ‌های متداول نوترونی بایستی از طریق تحقیقات بیشتر بررسی گردد.
کلیدواژه‌ها

عنوان مقاله English

Investigation of the shielding effectiveness of Polyvinyl Alcohol-Boron Carbide composite for 241Am-Be neutron source

نویسندگان English

Shahryar Malekie
Nahid Hajiloo
Fatemeh Dowlatshah
Radiation Application Research School, Nuclear Science and Technology Research Institute, Rajaee shahr, Karaj, Iran
چکیده English

Polymer composites because of lightness, easy processing, possessing a lot of hydrogen atoms due to elastic scattering with neutron particles are considered as suitable candidate to be used as moderator and shielding of the neutrons. In this experimental work, Polyvinyl Alcohol-Boron Carbide (PVA-B4C) composite with 5 wt% of filler particles was fabricated with 1.061 mm thickness via solution processing. The size of B4C particles used in this composite was relied between 20-50 μm. Then, the composite was exposed to 241Am-Be neutron source with average energy of 5 MeV and activity of 5 Ci. In order to measure the dose rate of neutrons, a 3He spherical detector at the distance of 100 cm was used. The measurement results showed that the total macroscopic cross-section of the mentioned composite was 0.208 cm⁻¹, which differs by 1.8% from the value obtained by MCNP simulation. Therefore, the use of this composite as a replacement for neutron conventional shields should be investigated through further research.

کلیدواژه‌ها English

PVA-B4C composite
Shielding
Neutrons
Americium-Beryllium
Total Macroscopic Cross-Section
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