Calculation of the role of Wigner energy in decontamination of Cs-۱۳۷ from irradiated Graphite pores
- سال انتشار: 1402
- محل انتشار: فصلنامه فیزیک و مهندسی پرتو، دوره: 4، شماره: 2
- کد COI اختصاصی: JR_RPE-4-2_007
- زبان مقاله: انگلیسی
- تعداد مشاهده: 102
نویسندگان
Nuclear Physics Group, Faculty of Basic Science, Comprehensive University of Imam Hossein, Tehran, Iran
Nuclear Physics Group, Faculty of Basic Science, Comprehensive University of Imam Hossein, Tehran, Iran
Nuclear Physics Group, Faculty of Basic Science, Comprehensive University of Imam Hossein, Tehran, Iran
Faculty of Nuclear Engineering, University of Shahid Beheshti, Tehran, Iran
Chemistry Group, Faculty of Basic Science, Comprehensive University of Imam Hossein, Tehran, Iran
چکیده
During the operation of Graphite -fuel HTGR (High-Temperature Gas-cooled Reactor) nuclear reactors, Graphite used as a neutron moderator, is irradiated and has a variety of contaminants (such as Cs-۱۳۷, Co-۶۰, and Sr-۹۰) and due to industrial and environmental considerations, decontamination of irradiated Graphite is very important. In this study, the decontamination of Cs-۱۳۷ trapped in Graphite pores of Graphite -fuel (HTGR) nuclear reactors has been analyzed. The proposed method for decontamination of irradiated Graphite surfaces is the thermal plasma-sputtering method with noble feed gases, which are used to reduce the risk of radioactive Graphite waste and in this regard, a mathematical model was developed to describe the process of decontamination of irradiated Graphite, which is prone to release Wigner energy due to defects and torsion caused by radiation. The results show that the decrease in radiation pollution of irradiated Graphite waste and various parameters of its decontamination process depend on the release of Wigner energy. The results obtained are in good agreement with the other researchers results.کلیدواژه ها
Decontamination, HTGR Reactor, Irradiated Graphite waste, Radionuclides, Cs-۱۳۷, Wigner Energy, mathematical modelاطلاعات بیشتر در مورد COI
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