Calculation of NaI(Tl) detector efficiency using Ra-226, Th-232, and K-40 radioisotopes: Three-phase Monte Carlo simulation study

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dc.authoridHüseyin Ozan Tekin / 0000-0002-0997-3488en_US
dc.authorscopusidHüseyin Ozan Tekin / 56971130700
dc.authorwosidHüseyin Ozan Tekin / J-9611-2016en_US
dc.contributor.authorTekin, Hüseyin Ozan
dc.contributor.authorAlmisned, Ghada
dc.contributor.authorIssa, Shams A. M.
dc.contributor.authorZakaly, Hesham M. H.
dc.contributor.authorKılıç, Gökhan
dc.contributor.authorEne, Antoaneta
dc.date.accessioned2022-07-06T08:11:24Z
dc.date.available2022-07-06T08:11:24Z
dc.date.issued2022en_US
dc.departmentİstinye Üniversitesi, Mühendislik ve Doğa Bilimleri Fakültesi, Bilgisayar Mühendisliği Bölümüen_US
dc.description.abstractThallium-activated sodium iodide (NaI(Tl)) detectors can be used in gamma cameras, environmental radiation assessments, including radiation emission levels from nuclear reactors, and radiation analysis equipment. This three-phase investigation aimed to model a standard NaI(Tl) detector using the Monte Carlo N-Particle eXtended (MCNPX) general-purpose Monte Carlo simulation techniques. Accordingly, a standard NaI(Tl) detector was designed along with the required properties. Next a validation study of the modelled NaI(Tl) detector has been performed based on the experimental results for absolute detector efficiency values obtained from Ra-226, Th-232, and K-40 radioisotopes. Our findings indicate that the obtained absolute detector efficiency values are quite close to used experimental values. Finally, we used the modelled detector for determination of mass attenuation coefficients of Ordinary concrete, Lead, Hematite-serpentine concrete, and Steel-scrap concrete at 186.1, 295.22, 351.93, 609.31, 1120.29, 1764.49, 238.63, 911.2, 2614, and 1460.83 keV gamma-ray energies. Additionally, according to our findings, mass attenuation coefficients obtained from the newly designed detector are compatible with the standard NIST (XCOM) data. To conclude, continuous optimisation procedures are strongly suggested for sophisticated Monte Carlo simulations in order to maintain a high degree of simulation reliability. As a result, it can be concluded that the validation of the simulation model is necessary using measured data. Finally, it can also be concluded that the validated detector models are effective instruments for obtaining basic gamma-ray shielding parameters such as mass attenuation coefficients.en_US
dc.identifier.citationTekin, H. O., ALMisned, G., Issa, S. A. M., Zakaly, H. M. H., Kilic, G., Ene, A. (2022). Calculation of NaI(Tl) detector efficiency using Ra-226, Th-232, and K-40 radioisotopes: Three-phase Monte Carlo simulation study. Open Chemistry, 20(1), 541-549.en_US
dc.identifier.doi10.1515/chem-2022-0169en_US
dc.identifier.endpage549en_US
dc.identifier.issn2391-5420en_US
dc.identifier.issue1en_US
dc.identifier.scopus2-s2.0-85133564061en_US
dc.identifier.scopusqualityQ2en_US
dc.identifier.startpage541en_US
dc.identifier.urihttps://doi.org/10.1515/chem-2022-0169
dc.identifier.urihttps://hdl.handle.net/20.500.12713/2985
dc.identifier.volume20en_US
dc.identifier.wosWOS:000817962500001en_US
dc.identifier.wosqualityQ3en_US
dc.indekslendigikaynakWeb of Scienceen_US
dc.indekslendigikaynakScopusen_US
dc.institutionauthorTekin, Hüseyin Ozan
dc.language.isoenen_US
dc.publisherDE GRUYTER POLAND SP Z O Oen_US
dc.relation.ispartofOPEN CHEMISTRYen_US
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/openAccessen_US
dc.subjectNaI(Tl) Detectoren_US
dc.subjectMCNPXen_US
dc.subjectAbsolute Detector Efficiencyen_US
dc.subjectScintillation Detectorsen_US
dc.titleCalculation of NaI(Tl) detector efficiency using Ra-226, Th-232, and K-40 radioisotopes: Three-phase Monte Carlo simulation studyen_US
dc.typeArticleen_US

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