Comparative analysis on application conditions of indium (III) oxide-reinforced glasses in nuclear waste management and source transportation: A Monte Carlo simulation study
dc.authorid | ZAKALY, Hesham M.H./0000-0002-7645-9964 | |
dc.authorid | ALMISNED, GHADA/0000-0001-9072-4480 | |
dc.authorid | Susoy, G/0000-0002-3760-1999 | |
dc.authorid | SEN BAYKAL, Duygu/0000-0001-9833-9392 | |
dc.authorid | Ene, Antoaneta/0000-0002-6976-0767 | |
dc.authorid | Tekin, Huseyin Ozan/0000-0002-0997-3488 | |
dc.authorid | KILIC, Gokhan/0000-0002-6762-6898 | |
dc.authorwosid | ZAKALY, Hesham M.H./E-8136-2016 | |
dc.authorwosid | ALMISNED, GHADA/AIF-4569-2022 | |
dc.authorwosid | Susoy, G/AAC-8014-2020 | |
dc.authorwosid | SEN BAYKAL, Duygu/ABH-1441-2021 | |
dc.authorwosid | Ene, Antoaneta/C-1386-2011 | |
dc.authorwosid | Tekin, Huseyin Ozan/J-9611-2016 | |
dc.authorwosid | KILIC, Gokhan/AAH-8955-2021 | |
dc.contributor.author | ALMisned, Ghada | |
dc.contributor.author | Baykal, Duygu Sen | |
dc.contributor.author | Kilic, G. | |
dc.contributor.author | Ilik, E. | |
dc.contributor.author | Rabaa, Elaf | |
dc.contributor.author | Susoy, G. | |
dc.contributor.author | Zakaly, Hesham M. H. | |
dc.date.accessioned | 2024-05-19T14:46:03Z | |
dc.date.available | 2024-05-19T14:46:03Z | |
dc.date.issued | 2023 | |
dc.department | İstinye Üniversitesi | en_US |
dc.description.abstract | 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 LenovoP620 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 | en_US |
dc.description.sponsorship | Princess Nourah Bint Abdulrahman University, Riyadh, Saudi Arabia [PNU RSP2023R149] | en_US |
dc.description.sponsorship | Princess Nourah Bint Abdulrahman University Researchers Supporting Project number (PNU RSP2023R149) , Princess Nourah Bint Abdulrahman University, Riyadh, Saudi Arabia. | en_US |
dc.identifier.doi | 10.1016/j.heliyon.2023.e14274 | |
dc.identifier.issn | 2405-8440 | |
dc.identifier.issue | 3 | en_US |
dc.identifier.pmid | 36950638 | en_US |
dc.identifier.scopus | 2-s2.0-85150032350 | en_US |
dc.identifier.scopusquality | Q1 | en_US |
dc.identifier.uri | https://doi.org10.1016/j.heliyon.2023.e14274 | |
dc.identifier.uri | https://hdl.handle.net/20.500.12713/5427 | |
dc.identifier.volume | 9 | en_US |
dc.identifier.wos | WOS:000970208200001 | en_US |
dc.identifier.wosquality | N/A | en_US |
dc.indekslendigikaynak | Web of Science | en_US |
dc.indekslendigikaynak | Scopus | en_US |
dc.language.iso | en | en_US |
dc.publisher | Cell Press | en_US |
dc.relation.ispartof | Heliyon | en_US |
dc.relation.publicationcategory | Makale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanı | en_US |
dc.rights | info:eu-repo/semantics/openAccess | en_US |
dc.snmz | 20240519_ka | en_US |
dc.subject | Nuclear Waste Management | en_US |
dc.subject | Container | en_US |
dc.subject | Mcnpx | en_US |
dc.subject | Nuclear Safety | en_US |
dc.subject | Indium (Iii) Oxide | en_US |
dc.title | Comparative analysis on application conditions of indium (III) oxide-reinforced glasses in nuclear waste management and source transportation: A Monte Carlo simulation study | en_US |
dc.type | Article | en_US |