Browsing by Author "Cakar, Nurtac"

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An Experimental Study on Gamma Radiation Attenuation Effectiveness of Magnetite and Serpentine Doped Ceramics
(Pergamon-elsevier Science Ltd, 2024) Oto, Berna; Cakar, Nurtac; Kavaz, Esra; Madak, Zekiye
The present study aims to investigate the gamma-ray (gamma) and fast neutrons attenuation characteristics of magnetite and serpentine doped ceramics via theoretical and experimental. gamma radiation permeability experiments were carried out by preparing a new type of ceramics with magnetite (M) and serpentine (S) additives [0 (C), 10 (M1; S1), 20 (M2; S2), 30 (M3; S3), wt %]. The fabricated shields were exposed to gamma radiation with 81, 160, 223, 302, 356 and 383 keV energies emitted from (133)Barium radioisotope and the measured intensities were detected by Canberra Ultra Ge detector. The parameters such as mass attenuation coefficients (mu(rho)), effective atomic numbers (Z(eff)), electron densities (N-el), half-value thickness (Delta(0.5)) and mean free path (lambda) characterizing the gamma shielding properties of the materials were determined. All theoretical gamma shielding parameters were calculated by running the EpiXS program. And also, exposure (EBF) and energy absorption (EABF) buildup factor values of ceramics were determined at different mean-free paths and photon energies using the EpiXS program. And finally, the macroscopic removal cross-section values (Sigma(R)) for fast neutrons of ceramics were computed. It was found that the density of the ceramic sample increases with the addition of ore. The values of (mu(rho)) are found to depend on the concentration of ore in the ceramics. The mu(rho) values of M3 ceramic are the highest whereas the mu(rho) values of C ceramic are the lowest in all studied ceramics. The M3 has the lowest half-value thickness (Delta(0.5)) and mean free path (lambda) values compared to other studied ceramics. The values of Z(eff) and N-el change as S3
An Experimental Study on the Radiation Shielding Properties of New Type Ceramics Containing Limonite and Hematite Minerals
(Elsevier Science Sa, 2025) Oto, Berna; Kavaz, Esra; Madak, Zekiye; Cakar, Nurtac
In this study, the development and evaluation of new ceramic materials doped with limonite and hematite minerals in terms of their effectiveness in gamma ray and neutron shielding was investigated. The primary aim is to determine gamma-ray shielding parameters for these ceramics, using gamma photon energies emitted from the Barium-133 radioisotope at specific energy levels (81, 160, 223, 302, 356, and 383 keV). Measurements were conducted using a Canberra Ultra Ge detector to detect the intensities of radiations. The mass attenuation coefficient (mu p), half-value thickness (A0.5), mean free path (2) and effective atomic numbers (Zeff) were determined experimentally and theoretically. And, exposure (EBF) and energy absorption (EABF) buildup factor values of ceramics were determined at different mean free paths and photon energies using the EpiXS program. Intercalarily, fast neutron attenuation parameters (ER) of ceramics have also been calculated. The densities of the ceramics increased with the addition of limonite and hematite minerals, ranging from 2.61 g/cm3 to 3.12 g/cm3 as the limonite content increased from 0 wt% to 30 wt %. Similar density variations were observed with the addition of hematite. There is a direct proportional relationship between the density of the ceramics and their shielding effectiveness. The effective atomic numbers (Zeff) were ranked as C G H1 G H2 G H3 G L1 G L2 G L3, indicating that the shielding effectiveness improves with higher doping levels. The L3 ceramic (with 30 % limonite addition) sample exhibited the highest fast neutron removal cross-section values among the tested samples. The findings demonstrate that doping ceramics with limonite and hematite minerals enhances their
Improvement of Nuclear Photon and Neutron Shielding Performance of Tm2o3 and Dy2o3 Doped Ceramics: an Experimental Study
(Pergamon-elsevier Science Ltd, 2024) Madak, Zekiye; Oto, Berna; Kavaz, Esra; Cakar, Nurtac
In this study, 60KAlSi3O8+10Al2Si2O5(OH)4+(30-x)SiO2+xA2O3 (x = 0, 10, 20, 30 wt% and A = Tm, Dy) ceramics were produced by conventional method to determine their usability as shielding material against ionized gamma radiation. To investigate the ionized photon shielding properties of the fabricated materials, the photon intensities (I and I0) were experimentally measured at 81, 160, 223, 302, 356, and 383 keV energies emitted from 133Barium radioisotope, and then the mass attenuation coefficient (mu p), The linear attenuation coefficients (mu, cm-1), half-value thickness (A0.5), mean free path (A), effective atomic numbers (Zeff) and electron densities (Nel) were derived experimentally. The obtained results were benchmarked with the calculated values from the EpiXS program. Also equivalent absorbed dose (EAD) values for fast neutrons were measured using BF3 gas proportional neutron detector from the Canberra NP-100B series and a241Am/Be neutron source with a 10 mCi activity. In addition, fast neutron shielding parameters (ER) of ceramics were also computed theoretically. The density of the fabricated ceramics varied from 2.607 g/cm3 to 4.392 g/cm3 when the Tm2O3 was raised from 0 wt% to 30 wt%. Likewise, with the addition of Dy2O3 compound, the densities of ceramics varied between 2.607 g/cm3 to 4.152 g/cm3. It was found that nuclear radiation shielding properties evolved by adding Tm2O3 and Dy2O3 compounds in the present ceramic.