تأثیر تابش گاما بر خواص فوتولومینسانس نیترید کربن بور و کاربرد آن در دزیمتری

نوع مقاله : مقاله پژوهشی

نویسندگان

پژوهشکده کاربرد پرتوها، پژوهشگاه علوم و فنون هسته‌ای، سازمان انرژی اتمی، تهران، ایران

10.22052/rsm.2025.256528.1103

چکیده

در این مطالعه نیترید کربن گرافیتی (g-C3N4) به روش بسپارش تراکمی حرارتی از دی‌سیان‌دی‌آمید تهیه شد. سپس نیترید کربن بور (BCN) با جایگزینی حرارتی اتم‌های کربن با اتم‌های بور زیر ساختار اسید بوریک در g-C3N4 به‌دست آمد. برای بررسی کارایی این ماده به‌عنوان دزیمتر، تغییرات در مشخصه فوتولومینسانس BCN تحت تابش گاما بررسی شد. نمونه‌ها با دزهای 100،50،30 و 200 گری در گاما سل با چشمه کبالت-60 پرتو دهی شدند. تغییرات در طیف فوتولومینسانس نمونه‌های پرتو دهی شده با کمک یک مدل برازش غیر خطی کمی سازی شد. طیف فوتولومینسانس هر نمونه به 6 پیک گوسی تجزیه شد و تفاوت نسبی در پارامترهای هر یک از این پیک‌ها پس از پرتو‌دهی نسبت به نمونه پرتودهی نشده بررسی شد. نتایج نشان داد که تفاوت نسبی در شدت فوتولومینسانس بصورت خطی با دز جذبی تغییر می‌کند و حساسیت آن به دز برای دزیمتری در محدوده 30 تا 200 گری مناسب است. ضریب همبستگی برای منحنی کالیبراسیون 99/0 به‌دست آمد.

کلیدواژه‌ها

عنوان مقاله [English]

The effect of gamma radiation on the photoluminescence properties of boron carbon nitride and its application in dosimetry

نویسندگان [English]

  • Sepideh Shafiei
  • Sodeh Sadjadi
  • Elham Mohagheghpour
Radiation Application Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran.
چکیده [English]

In this study, graphitic carbon nitride (g-C3N4) was synthesized through thermal polycondensation of dicyandiamide. Boron carbon nitride (BCN) was then obtained via thermal substitution of carbon atoms with boron atoms of boric acid substructures in g-C3N4. The efficacy of this material as a dosimeter was investigated by examining the changes in the photoluminescence characteristics of BCN when exposed to gamma irradiation. The samples were irradiated with doses of 30, 50, 100, and 200 gray in a gamma cell with a cobalt-60 source. The changes in the photoluminescence spectrum of the irradiated samples were quantified using a nonlinear fitting model. Each sample’s photoluminescence spectrum was deconvoluted into 6 Gaussian peaks, and the relative differences in the parameters of each peak after irradiation were compared to the unirradiated sample. The results indicated that the relative difference in photoluminescence intensity changes linearly with the dose, and its sensitivity to the dose is suitable for dosimetry in the range of 30 to 200 gray. The correlation coefficient for the calibration curve was 0.99.

کلیدواژه‌ها [English]

  • Dosimetry
  • Thermoluminescence
  • Zinc Phosphate
  • Copper impurity
  • Gamma radiation
  • Dose response

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