A rapid and direct method for half value layer calculations for nuclear safety studies using MCNPX Monte Carlo code

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dc.authoridHüseyin Ozan Tekin / 0000-0002-0997-3488en_US
dc.authorscopusidHüseyin Ozan Tekin / 56971130700en_US
dc.authorwosidHüseyin Ozan Tekin / J-9611-2016
dc.contributor.authorTekin, Hüseyin Ozan
dc.contributor.authorAlmisned, Ghada
dc.contributor.authorIssa, Shams A.M.
dc.contributor.authorZakaly, Hesham M.H.
dc.date.accessioned2022-06-16T11:56:05Z
dc.date.available2022-06-16T11:56:05Z
dc.date.issued2022en_US
dc.departmentİstinye Üniversitesi, Mühendislik ve Doğa Bilimleri Fakültesi, Bilgisayar Mühendisliği Bölümüen_US
dc.description.abstractHalf Value Layer calculations theoretically need prior specification of linear attenuation calculations, since the HVL value is derived by dividing ln(2) by the linear attenuation coefficient. The purpose of this study was to establish a direct computational model for determining HVL, a vital parameter in nuclear radiation safety studies and shielding material design. Accordingly, a typical gamma-ray transmission setup has been modeled using MCNPX (version 2.4.0) general-purpose Monte Carlo code. The MCNPX code's INPUT file was designed with two detection locations for primary and secondary gamma-rays, as well as attenuator material between those detectors. Next, Half Value Layer values of some well-known gamma-ray shielding materials such as lead and ordinary concrete have been calculated throughout a broad gamma-ray energy range. The outcomes were then compared to data from the National Institute of Standards and Technology. The Half Value Layer values obtained from MCNPX were reported to be highly compatible with the HVL values obtained from the NIST standard database. Our results indicate that the developed INPUT file may be utilized for direct computations of Half Value Layer values for nuclear safety assessments as well as medical radiation applications. In conclusion, advanced simulation methods such as the Monte Carlo code are very powerful and useful instruments that should be considered for daily radiation safety measures. The modeled MCNPX input file will be provided to the scientific community upon reasonable request. © 2022 Korean Nuclear Societyen_US
dc.identifier.citationTekin, H. O., ALMisned, G., Issa, S. A. M., & Zakaly, H. M. H. (2022). A rapid and direct method for half value layer calculations for nuclear safety studies using MCNPX monte carlo code. Nuclear Engineering and Technology, doi:10.1016/j.net.2022.03.037en_US
dc.identifier.doi10.1016/j.net.2022.03.037en_US
dc.identifier.issn1738-5733en_US
dc.identifier.scopus2-s2.0-85128259113en_US
dc.identifier.scopusqualityQ2en_US
dc.identifier.urihttps://doi.org/10.1016/j.net.2022.03.037
dc.identifier.urihttps://hdl.handle.net/20.500.12713/2909
dc.identifier.wosWOS:000862955100014en_US
dc.identifier.wosqualityQ1en_US
dc.indekslendigikaynakWeb of Scienceen_US
dc.indekslendigikaynakScopusen_US
dc.institutionauthorTekin, Hüseyin Ozan
dc.language.isoenen_US
dc.publisherKorean Nuclear Societyen_US
dc.relation.ispartofNuclear Engineering and Technologyen_US
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/openAccessen_US
dc.subjectHalf Value Layeren_US
dc.subjectMCNPXen_US
dc.subjectMonte Carlo Simulationsen_US
dc.subjectRadiation Safetyen_US
dc.titleA rapid and direct method for half value layer calculations for nuclear safety studies using MCNPX Monte Carlo codeen_US
dc.typeArticleen_US

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