نوع مقاله : مقاله پژوهشی کامل
نویسندگان
1 گروه فیزیک، دانشکده علوم پایه، دانشگاه بین المللی امام خمینی (ره)، قزوین، ایران
2 گروه فیزیک تجربی و کاربردی، پژوهشکده فیزیک و شتابگرها، پژوهشگاه علوم و فنون هستهای، تهران، ایران
3 گروه فیزیک، دانشکده علوم پایه، دانشگاه زنجان، زنجان، ایران
4 پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، تهران، ایران
چکیده
کلیدواژهها
موضوعات
عنوان مقاله [English]
نویسندگان [English]
The feasibility of producing the iridium-192 radioisotope has been investigated in this work. Iridium-192 has various applications in nuclear medicine, particularly in brachytherapy. To increase the production yield and the high purity of this product, the direct production parameters of this radioisotope were studied based on the 191Ir (n,γ) 192Ir reaction. It is crucial to determine the appropriate irradiation location according to the neutron flux and the cross-section of the neutron reaction with the target material. By analyzing the experimental spectrum of neutrons exiting the reactor, as well as simulating the reactor using the MCNPX code, detailed information was obtained on the flux and spectrum of thermal neutrons and the irradiation sites. Calculations related to the flux of thermal neutrons were performed both theoretically and through simulation. Considering the information obtained from the simulation and comparing it with the experimental diagram of the reaction cross-section, the optimal irradiation site for the production of iridium-192 was determined. By comparing the simulation results related to the final activity at different reactor locations, the best site for producing iridium-192 with the highest activity was also identified.
کلیدواژهها [English]