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Öğe Characterization of a broad range gamma-ray and neutron shielding properties of MgO-Al2O3-SiO2-B2O3 and Na2O-Al2O3-SiO2 glass systems(Elsevier Science Bv, 2019) Tekin, H. O.; Kavaz, E.; Altunsoy Güçlü, E. E.; Kamışlıoğlu, M.; Kılıçoğlu, O.; Ağar, Osman; Sayyed, M. I.In this research, the radiation shielding parameters for two glass systems with composition of 20MgO-(20-x)Al2O3-57SiO(2)-3B(2)O(3)-xCr(2)O(3) (x = 0, 0.1, 0.25, 0.5 and 1 mol%) and Na2O-Al2O3 SiO2 glasses were studied. For this purpose, a scintillation detector namely 3 x 3 inch NaI(Tl) has been designed for detection of photons through MCNPX simulation code. Thus, the mass attenuation coefficients (mu/rho) and some other gamma shielding quantities were calculated. The estimated MCNPX data of all the glasses were compared and approved with those of WinXCOM program. The gamma ray buildup factors for the two glass systems were also determined in a wide energy range of 0.02-15 MeV for penetration depths up to 15 mfp. The results revealed that the mass attenuation coefficients for the glass samples in the first glass system are higher than those in the glasses in the second system and thus the glasses coded as MASBC have more ability in reducing radiation than NAS glasses. Among the selected glasses, C4 has the largest values of mu(rho) and lowest half value layer, and therefore this glass sample has better shielding features than other samples. Besides, 3-1 glass sample has the lowest values; therefore this sample has the least ability to block and reduce the incoming gamma radiation. The results also showed that the effective atomic number (Z(eff)) of the glasses in the first composition increased with increasing the content of Cr2O3, and Zeff in the second glass system (i.e. NAS) increased with increasing the Al2O3 content. The values of mass removal cross section for neutron (Sigma(R)) vary between 0.09112 and 0.09163 and 0.08415-0.08710 for the first and second glass system respectively. The obtained results from the present investigation can be useful to understanding of influence of Cr2O3 and Al2O3 additive on nuclear radiation shielding properties of tellurite MgO-Al2O3-SiO2-B2O3 and Na2O-Al2O3-SiO2 glasses.Öğe Characterization of SiO2-PbO-CdO-Ga2O3 glasses for comprehensive nuclear shielding performance: Alpha, proton, gamma, neutron radiation(Elsevier Sci Ltd, 2019) Tekin, H. O.; Kavaz, E.; Papachristodoulou, Athanasia; Kamışlıoğlu, M.; Ağar, Osman; Guclu, E. E. Altunsoy; Kılıçoğlu, O.The present study focuses on the results on survey of exposure buildup factor, photon and neutron shielding parameters for B, C and D series SiO2-PbO-CdO-Ga2O3 glasses utilizing MCNPX Monte Carlo code. In order to check out the accuracy of MCNPX results, the computational values of mass attenuation coefficients were confirmed with those of XCOM database in relatively photon energy region of 0.020-20 MeV. The relative deviation between MCNPX and XCOM values is below 10% except for 0B and 2B at 0.060 MeV and 0D and 1D at 0.122 MeV. The gamma ray buildup factors for the three extended glass systems were also determined in a wide energy range of 0.02-15 MeV for penetration depths up to 15 mfp. In addition, some related radiation attenuation parameters have been estimated and deduced that among the selected glasses, C-series sample has best photon shielding performance while being B series glasses the superior materials for neutron, alpha and proton shielding. The results showed that C series glass samples among SPCG glasses have clear advantage in weight decrease in terms of shielding the X- and gamma rays in relatively photon energy region of 0.020-20 MeV. It can be concluded that certain types of glasses which include this kind of mixture may be considered an alternative material for radiation shielding practices.Öğe Er 2 O 3 effects on photon and neutron shielding properties of TeO 2 -Li 2 O-ZnO-Nb 2 O 5 glass system(Elsevier B.V., 2019) Ağar, Osman; Kavaz, E.; Altunsoy Güçlü, E. E.; Kılıçoğlu, O.; Tekin, H.O.; Sayyed, M.I.; Ergüzel, T.T.In this study, a series of 75TeO 2 -5Li 2 O-10ZnO-(10-x)Nb 2 O 5 -(x)Er 2 O 3 (where x = 0, 0.5, 1.0, 1.5, 2.0 and 2.8 mol%) glasses have been surveyed in terms of photon and neutron shielding characteristics. For this aim, 3 × 3 inch NaI(Tl) detector has been simulated in order to detect photons. Afterwards, the mass attenuation coefficients (?/?) and some shielding quantities such as half-value layer (HVL), tenth value layer (TVL), mean free path (MFP), effective atomic number (Z eff ), effective electron density (N el ), equivalent atomic number (Zeq) and exposure build-up factor (EBF) have been calculated. The obtained MCNPX results of all the glasses have been compared and approved with those of XCOM program. Also, their gamma ray buildup factors have been determined in a wide energy range of 0.02–20 MeV for penetration depths up to 15 mfp. Moreover, neutron attenuation abilities of glasses have been evaluated by estimating neutron total effective removal cross section. The results showed that Er 2 O 3 partial replacement of Nb 2 O 5 in 75TeO 2 -5Li 2 O-10ZnO-(10- x)Nb 2 O 5 -(x)Er 2 O 3 glass system enhances photon and neutron attenuation characteristics. It can be deduced that obtained results from the present investigation can be useful to understanding of influence of Er 2 O 3 on nuclear radiation shielding properties of tellurite glasses.Öğe An extensive investigation on gamma-ray and neutron attenuation parameters of cobalt oxide and nickel oxide substituted bioactive glasses(Elsevier Sci Ltd, 2019) Tekin, H. O.; Kavaz, E.; Altunsoy Güçlü, E. E.; Kılıçoğlu, O.; Ağar, Osman; Ergüzel, T. T.; Sayyed, M., IThis study aimed to investigate the gamma-ray and neutron attenuation parameters of cobalt oxide and nickel oxide substituted ten bioactive glasses. The mass attenuation coefficient (mu/rho) for the selected bioactive glasses was calculated using MCNPX code in photon energy range (0.02 MeV - 20 MeV) and the results were compared with the output of WinXcom software. Other vital gamma-ray attenuation parameters such as half value layer (HVL), tenth value layer (TVL), mean free path (MFP), effective atomic number (Z(eff)), and effective electron density (N-ei) for the selected bioactive glasses were also calculated for each approach. Gamma-ray and neutron transmission factors as well as neutron effective removal cross-sections of each bioactive glass (Sigma R) were also taken into consideration to underline the distinctive parameters. Additionally, exposure buildup factor (EBF) values were found with G-P fitting approach depending on the energy and penetration depths. The results points that, the lowest HVL, TVL and MFP values and the highest neutron effective removal cross-sections (Sigma(R)) values are the characteristics of NiO-4C and CoO-4. The results indicate that the density of the material affects the photon and neutron interaction parameters. While NiO-4C has the lowest TF values for both gamma and neutron radiation, the highest Sigma(R) values are collected from NiO-4C glass material. The gamma and neutron transmission factors (TF) of the studied bioactive glasses support the aforementioned results. The lowest Z(eff) values were generated for 45S5C and 45S5 ordinary glasses, while CoO-4 and NiO-4C doped glasses are having the highest values of Z(eff). EBF values of the glasses were also calculated in the energy range 0.015-15 MeV up to 40 mfp. The smallest EBF values were measured for CoO-4 and NiO-4C glasses. It can be concluded that NiO-4C bioactive glass outperformed compared to other studied samples and is a promising bioactive glass for gamma-ray and neutron attenuation.Öğe An extensive study on nuclear shielding performance and mass stopping power (MSP)/projected ranges (PR) of some selected granite samples(Taylor & Francis Ltd., 2020) Tekin, H. O.; Kavaz, E.; Sayyed, M. I.; Ağar, Osman; Kamıslıoğlu, M.; Altunsoy Güçlü, E. E.; Eke, C.In the present investigation, mass attenuation coefficients (mu(m)) and some related nuclear shielding quantities of various granite samples have been computed at several photon energies of 0.356, 0.662, 1.173, 1.274 and 1.333 MeV by using standard simulation geometry of the Monte Carlo N-particle Transport Code System - extended (MCNPX) code. The estimated data have been compared to those of experimental and NIST standard theoretical. The results are observed to be comparable with each other. This study represented that G1 and G9 granites possess the highest and lowest half-layer value (HVL) among the selected granite samples, respectively. The values of effective atomic number (Z(eff)) of all the granites were found to be almost stationary in the studied energy region. In addition, exposure buildup factor (EBF) values of the granites were computed for the 0.015-15 MeV energy range up to 40 mfp. The largest and lowest values for EBF were obtained for G8 and G2 samples, respectively. The HVLs of nine granite samples were compared with those of concretes, rocks and polyethylene composites at different photon energies. Additionally, mass stopping power (MSP) and projected range (PR) are calculated using the Stopping and Range of Ions in Matter code. The effective removal cross-sections for fast neutrons (sigma(R)) have been also assessed to survey the neutron protection effectiveness of the granites. The results represented that G9 has the best neutron attenuation features. It can be concluded from this study that the G9 granite sample possesses superior gamma and neutron shielding performances.Öğe The investigation of gamma-ray and neutron shielding parameters of Na 2 O-CaO-P 2 O 5 -SiO 2 bioactive glasses using MCNPX code(Elsevier B.V., 2019) Tekin, H.O.; Kılıçoğlu, O.; Kavaz, E.; Altunsoy Güçlü, E. E.; Almatari, M.; Ağar, Osman; Sayyed, M.I.Bioactive glasses are silicate glasses with sodium, calcium and phosphorus in its composition used to fulfill or support the functions of living tissues in the human body. The superiority of physical and mechanical properties of the bioactive glasses leads to the opportunity to use for radiation protection. From this point of view, radiation absorption parameters of nine bioactive glasses were reported in the present research. The mass attenuation coefficient (?/?) for the selected bioactive glasses was calculated using MCNPX simulation code in the photon energy range 0.02–20 MeV and the results were compared with XCOM data. The values of ?/? calculated in two methods were found to support each other. Other vital parameters like half and tenth value layer (HVL and TVL), mean free path (MFP) and effective atomic number (Z eff ) for the selected bioactive glasses were also evaluated by utilizing the ?/?. ICSW9 glass with more phosphate and sodium contents possess the lowest MFP, HVL and TVL values while has the highest Z eff values among the bioactive glasses under study. To evaluate the neutron protection performance of investigated bioactive glasses, effective removal cross-section values (?R) have been determined. The results showed that ICSW9 has also superior neutron attenuation properties. Additionally, exposure buildup factor (EBF) values were found with G-P fitting approach depending on the energy and penetration depths. The bioactive glasses with further equivalent atomic number possesses the minimum value of EBF. © 2019 The AuthorsÖğe The Mass stopping power / projected range and nuclear shielding behaviors of barium bismuth borate glasses and influence of cerium oxide(Elsevier Ltd, 2019) Kavaz, E.; Tekin, H.O.; Ağar, Osman; Altunsoy Güçlü, E. E.; Kılıçoğlu, O.; Kamışlıoğlu, M.; Abuzaid, M.M.This paper aims to evaluate not only photon and neutron but also proton and alpha shielding effectiveness of barium bismuth borate glasses doped by CeO2. The mass attenuation coefficients (?/?) of these glasses have been computed utilizing MCNPX (2.6.0) code in a wide energy range of 0.02–20 MeV and compared with the results of WinXCOM software. Afterwards, some photon attenuation parameters such as half-value layer, (HVL), tenth-value layer (TVL), mean free path (MFP), effective atomic number (Zeff), effective electron density (Nel), photon transmission factors (TF) and neutron effective removal cross-sections (?R) for the cerium oxide substituted barium bismuth borate glasses have been estimated. Using G-P fitting method, exposure buildup factor (EBF) values have been found over the energy range 0.015–15 MeV up to 40 mfp. In addition, Mass stopping power (MSP) and projected range (PR) values have been calculated for proton particles (H1) and alpha particles (He+2). The results exhibit that the density of the glass can be related to the photon and neutron shielding. A10 glass has the highest ?R values whereas the lowest TF values in gamma and neutron radiation have been observed for A1 sample. A1 and U glasses possess the highest values of Zeff as well as the smallest values of EBF. It can be concluded that A1 and A10 glasses are alternative materials with terms of photon and neutron attenuation, respectively.Öğe Photon and neutron shielding performance of boron phosphate glasses for diagnostic radiology facilities(Elsevier Science Bv, 2019) Tekin, H. O.; Altunsoy Güçlü, E. E.; Kavaz, E.; Sayyed, M. I.; Ağar, Osman; Kamışlıoğlulu, M.This study focuses on radiation shielding characteristics of Li2O, Al2O3 and ZnO-doped boron phosphate glasses containing PbO and Bi2O3. Mass attenuation coefficient (mu/rho) values of the glasses have been calculated using MCNPX code at various photon energies ranging from 60 to 120 keV and compared to those of XCOM software. The obtained results exhibited that MCNPX and XCOM are in good agreement at all energies. Some shielding parameters such as effective atomic number (Z(eff)), effective electron density (N-el), half value layer (HVL), mean free path (MFP) and Photon transmission factors (TF-photon) were determined using the obtained mass attenuation coefficients. Moreover, macroscopic effective removal cross sections (Sigma R) and neutron transmission factors (TF-neutron) for fast neutrons have been evaluated. To simulate the attenuation properties of investigated glasses in a diagnostic radiology operation facility (control room), each boron phosphate glass sample was placed in front of a mathematical human head phantom namely SNYDER. For the glasses under examination, average photon flux in the eight detection points, which were located in different points of SNYDER head phantom, was calculated. Among the studied glasses, BPM4 sample has showed superior photon and neutron radiation shielding effectiveness. It can be concluded that boron-doped glasses are superior shielding materials for both gamma ray and neutrons.
