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Comparative analysis on application conditions of indium (III) oxide-reinforced glasses in nuclear waste management and source transportation: A Monte Carlo simulation study

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Заглавие Comparative analysis on application conditions of indium (III) oxide-reinforced glasses in nuclear waste management and source transportation: A Monte Carlo simulation study
 
Автор ALMisned, G.
Baykal, D. S.
Kilic, G.
Ilik, E.
Rabaa, E.
Susoy, G.
Zakaly, H. M. H.
Ene, A.
Tekin, H. O.
 
Тематика CONTAINER
INDIUM (III) OXIDE
MCNPX
NUCLEAR SAFETY
NUCLEAR WASTE MANAGEMENT
 
Описание 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. © 2023 The Authors
Princess Nourah Bint Abdulrahman University, PNU
Princess Nourah Bint Abdulrahman University Researchers Supporting Project number (PNU RSP2023R149), Princess Nourah Bint Abdulrahman University, Riyadh, Saudi Arabia.
 
Дата 2024-04-05T16:17:36Z
2024-04-05T16:17:36Z
2023
 
Тип Article
Journal article (info:eu-repo/semantics/article)
|info:eu-repo/semantics/publishedVersion
 
Идентификатор Almisned, G, Baykal, DS, Kilic, G, Ilik, E, Rabaa, E, Susoy, G, Zakaly, HMH, Ene, A & Tekin, HO 2023, 'Comparative analysis on application conditions of indium (III) oxide-reinforced glasses in nuclear waste management and source transportation: A Monte Carlo simulation study', Heliyon, Том. 9, № 3, e14274. https://doi.org/10.1016/j.heliyon.2023.e14274
Almisned, G., Baykal, D. S., Kilic, G., Ilik, E., Rabaa, E., Susoy, G., Zakaly, H. M. H., Ene, A., & Tekin, H. O. (2023). Comparative analysis on application conditions of indium (III) oxide-reinforced glasses in nuclear waste management and source transportation: A Monte Carlo simulation study. Heliyon, 9(3), [e14274]. https://doi.org/10.1016/j.heliyon.2023.e14274
2405-8440
Final
All Open Access, Gold, Green
https://www.scopus.com/inward/record.uri?eid=2-s2.0-85150032350&doi=10.1016%2fj.heliyon.2023.e14274&partnerID=40&md5=6fe184fb994cbe8744addcc12d651f52
http://www.cell.com/article/S2405844023014810/pdf
http://elar.urfu.ru/handle/10995/130278
10.1016/j.heliyon.2023.e14274
85150032350
000970208200001
 
Язык en
 
Права Open access (info:eu-repo/semantics/openAccess)
cc-by-nc-nd
https://creativecommons.org/licenses/by-nc-nd/4.0/
 
Формат application/pdf
 
Издатель Elsevier Ltd
 
Источник Heliyon
Heliyon