Comparative analysis on application conditions of indium (III) oxide-reinforced glasses in nuclear waste management and source transportation: A Monte Carlo simulation study
Ghada ALMisned,
Duygu Sen Baykal,
G. Kilic,
E. Ilik,
Elaf Rabaa,
G. Susoy,
Hesham M.H. Zakaly,
Antoaneta Ene,
H.O. Tekin
Affiliations
Ghada ALMisned
Department of Physics, College of Science, Princess Nourah Bint Abdulrahman University, P.O. Box 84428, Riyadh, 11671, Saudi Arabia
Duygu Sen Baykal
Istanbul Kent University, Vocational School of Health Sciences, Medical Imaging Techniques, Istanbul, 34433, Turkiye
G. Kilic
Eskisehir Osmangazi University, Faculty of Science, Department of Physics, Eskisehir, 26040, Turkiye
E. Ilik
Eskisehir Osmangazi University, Faculty of Science, Department of Physics, Eskisehir, 26040, Turkiye
Elaf Rabaa
Medical Diagnostic Imaging Department, College of Health Sciences, University of Sharjah, Sharjah, 27272, United Arab Emirates
G. Susoy
Department of Physics, Faculty of Science, Istanbul University, 34134, Istanbul, Turkey
Hesham M.H. Zakaly
Institute of Physics and Technology, Ural Federal University, 620002, Ekaterinburg, Russia; Physics Department, Faculty of Science, Al-Azhar University, Assiut, 71524, Egypt
Antoaneta Ene
INPOLDE Research Center, Department of Chemistry, Physics and Environment, Faculty of Sciences and Environment, Dunarea de Jos University of Galati, 47 Domneasca Street, 800008, Galati, Romania; Corresponding author. INPOLDE Research Center, Department of Chemistry, Physics and Environment, Faculty of Sciences and Environment, Dunarea de Jos University of Galati, 47 Domneasca Street, 800008, Galati, Romania.
H.O. Tekin
Medical Diagnostic Imaging Department, College of Health Sciences, University of Sharjah, Sharjah, 27272, United Arab Emirates; Istinye University, Faculty of Engineering and Natural Sciences, Computer Engineering Department, Istanbul, 34396, Turkiye; Corresponding author. Medical Diagnostic Imaging Department, College of Health Sciences, University of Sharjah, Sharjah, 27272, United Arab Emirates.
This study's primary objective is to provide the preliminary findings of novel research on the design of Indium (III) oxide-reinforced glass container that were thoroughly developed for the purpose of a nuclear material container for transportation and waste management applications. The shielding characteristics of an Indium (III) oxide-reinforced glass container with a certain elemental composition against the 60Co radioisotope was thoroughly evaluated. The energy deposition in the air surrounding the designed portable glass containers is measured using MCNPX general-purpose Monte Carlo code. Simulation studies were carried out using Lenovo-P620 workstation and the number of tracks was defined as 108 in each simulation phase. According to results, the indium oxide-doped C6 (TZI8) container exhibits superior protective properties compared to other conventional container materials such as 0.5Bitumen-0.5 Cement, Pb Glass composite, Steel-Magnetite concrete. In addition to its superiority in terms of nuclear safety, it is proposed that the source's simultaneous observation and monitoring, as well as the C6 (TZI8) glass structure's transparency, be underlined as significant advantages. High-density glasses, which may replace undesirable materials such as concrete and lead, provide several advantages in terms of production ease, non-toxic properties, and resource monitoring. In conclusion, the use of Indium (III) oxide-reinforced glass with its high transparency and outstanding protection properties may be a substantial choice in places where concrete is required to ensure the safety of nuclear materials.
