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Bi2O3 B2O3 ZnO BaO Li2O glass system for gamma ray shielding applications
(Elsevier, 2020) Sayyed, M., I.; Tekin, H. O.; Taki, Malaa M.; Mhareb, M. H. A.; Ağar, Osman; Sakar, E.
In order to investigate new candidate glasses for gamma shielding application, we synthesized a number of glasses with composition of (50 + x)Bi2O3-(30-x)B2O3-10ZnO-5BaO-5Li(2)O where x = 10, 15 and 20, all in mol%. We used the conventional melt-quenching-annealing technique with melting temperature at 975 degrees C and 300 degrees C for 30 min and 5 h, respectively. Density and other important physical properties have been measured and calculated using related methods and formulas. Moreover, X-ray diffraction have been utilized for all samples to explore the structure of these glasses, the XRD profile have been recorded between 10 degrees to 80 degrees for all samples, while the functional groups of the elements evolved in these glasses have been studied using FTIR with the range of 4000-400 cm(-1). Additionally, optical absorption for the synthesized glasses have been measured in the range of 200-800 nm to investigate the cut-off wavelength and optical band gap. Besides, the mass attenuation coefficient values of the present glasses have been estimated through WinXCom software as well as MCNPX computer code and the obtained results were used to determine the effective atomic number (Z(eff)), the half value layer (HVL) and the mean free path (MFP). From the derived results, it was found that S3 is the superior glass sample in terms of shielding performance on account of larger Z(eff) values and lower MFP/HVL values among the investigated glasses. The present glasses indicate potentiality to be evaluated as shielding absorbers and for an improved shielding effectiveness of the Bi2O3-B2O3-ZnO-BaO-Li2O glasses, a large Bi2O3 concentration would be required.
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.
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.
A comparative study on gamma photon shielding features of various germanate glass systems
(Elsevier Sci Ltd, 2019) Dong, M. G.; Ağar, Osman; Tekin, H. O.; Kılıçoğlu, O.; Kaky, Kawa M.; Sayyed, M. I.
In this paper, we studied the gamma photon attenuation properties for different germanate glasses systems with composition Sb2O3-GeO2-SiO2-Al2O3, TeO2-WO3-GeO2, GeO2-TeO2/SiO2-PbO-CaO-Tm2O3 and B2O3-GeO2-Gd2O3-Eu2O3-GdF3-BaF2. The mass attenuation coefficients (mu/rho) for the selected germanate glasses were calculated at different energies (between 0.015 MeV and 15 MeV) using the MCNPX code. The calculated MCNPX mu/rho values then compared with the WinXCom data to check the accuracy in the results. The results showed that the Sb2O3 replacement by SiO2 causes a decrease in mu/rho for Sb2O3-GeO2-SiO2-Al2O3 glass system. Also, it is found that for TeO2-WO3-GeO2 glass system, mu/rho decreases as GeO2 content increases from 1 to 20 mol%. While for GeO2-TeO2/SiO2-PbO-CaO-Tm2O3 glass system, the results revealed that the glass samples contain TeO2 possess higher mu/rho values than the samples contain SiO2. For the B2O3-GeO2-Gd2O3-Eu2O3-GdF3-BaF2 glasses, we found that the mu/rho values decrease as BaF2 is increased from 0 to 15 mol%. Moreover, it is found that 5OSb-OGe for series 1, TWGO for series 2, 2G4T for series 3 and X = 0 for series 4 glass samples among the studied glasses have the highest effective atomic number values. On the basis of the results achieved, 50Sb-OGe, TWGO, 2G4T and X = 0 samples have the best radiation shielding characteristics among the selected glasses.
Evaluation of gamma-ray and neutron shielding features of heavy metals doped Bi2O3-BaO-Na2O-MgO-B2O3 glass systems
(Elsevier, 2020) Sayyed, M. I.; Kumar, Ashok; Tekin, H. O.; Kaur, Ramandeep; Singh, Mandeep; Ağar, Osman
Recognizing the vast uses of radioactive sources in several sectors such as industry, medicine, agriculture, development of effective radiation shielding material finds great significance. Present work is aimed to explore potential glass based material for neutron and gamma ray shielding applications. In the present study, several borate glasses with composition of (20 + x) Bi2O3-20BaO-10Na(2)O-10MgO-(40-x) B2O3 (where x = 0, 5, 10, 15 and 20 mol%) were successfully synthesized via melt-quenching method, and evaluated their gamma-ray and neutron shielding features. The densities of the studied glasses are increased with the addition of Bi2O3 content. The non-existence of any sharp peak in X-ray diffraction spectra confirms the amorphous nature of the glasses. Fourier transform infrared spectroscopy gives the necessary information regarding the structure of the glasses. The optical band gap for both direct and indirect transitions decreases from 2.905 to 2.806 eV and 2.661 to 2.536 eV as B2O3 replaced with Bi2O3. Some quantities namely mass attenuation coefficients (mu/rho), half-value layer (HVL), mean free path (MFP), macroscopic effective removal cross sections (Sigma(R)) and transmission factor (TF) have been studied theoretically and computationally for gamma-ray and neutron shielding characteristics. The correlation coefficient (R-2) values between the XCOM and MCNPX results of all the glasses were found to be almost 1. According to our results, Bi40B20 sample with the highest amount of Bi2O3 has the lowest MFP and TF values, and this suggested that the gamma and neutron shielding performances of the Bi2O3-BaO-Na2O-MgO3-B2O3 glasses are improved with the addition of Bi2O3 content.
Evaluation of the shielding parameters of alkaline earth based phosphate glasses using MCNPX code
(Elsevier Science Bv, 2019) Ağar, Osman; Khattari, Z. Y.; Sayyed, M. I.; Tekin, H. O.; Al-Omari, S.; Maghrabi, M.; Zaid, M. H. M.
Glass systems of composition 16XO-3Al(2)O(3)-6CuO-20Na(2)O-55P(2)O(5) (where X = Sr, Ca, Mg and Ba mol%) have been investigated to check its potential utilize as gamma ray shielding material. Different shielding quantifies namely mass attenuation coefficient (mu/rho), effective atomic number (Z(eff)), half value layer (HVL) and mean free path (MFP) have been evaluated using MCNPX code and XCOM program at different photon energies between 0.015 and 10 MeV. The obtained data revealed good agreement between the mu/rho values derived from XCOM and MCNPX code (version 2.6.0). It is found that the mass attenuation coefficients of BaO-doped phosphate glass are higher than those of the other alkaline earth elements-doped glasses, whereas MgO possess the lowest values. This indicates that the BaO-doped phosphate glass is the superior gamma radiation attenuator among the studied glass samples. The gamma shielding performance of the glasses under study has been compared to some commercial glasses and different concrete samples in terms of MFP.
Experimental studies and Monte Carlo simulations on gamma ray shielding competence of (30+x)PbO-10WO(3)-10Na(2)O-10MgO-(40-x)B2O3 glasses
(Elsevier, 2020) Kumar, Ashok; Gaikwad, D. K.; Obaid, Shamsan S.; Tekin, H. O.; Ağar, Osman; Sayyed, M. I.
In the present study, we utilized the melt quenching method to fabricate (30 + x)PbO-10WO(3)-10Na(2)O -10MgO-(40-x)B2O3 (where x = 0, 5, 10, 15 and 20 mol %) glasses. The mass attenuation coefficients (mu/rho) have been measured at four energies using gamma spectrometric system and the measured values were validated by MCNPX code and XCOM software. The variation in the experimental, theoretical and MCNPX mu/rho values coincided with each other in all energy regions. The linear attenuation coefficient values for the prepared glasses are proportional to the increase of PbO concentration; however reduce with the increasing photon energy. Besides, we found that the addition of PbO to the glasses leads to reduce in HVL values in the photon energy range, which suggested that the addition of PbO in the synthesized glasses enhances property of more photons absorption of the glass samples. The effective atomic number (Z(eff)) for the prepared glasses was also calculated and then, we discussed the effect of PbO on the Z(eff). The Z(eff) values lie within range of 29.95-42.77, 20.90 to 30.88, 17.99 to 26.46, and 17.74 to 26.07 for 0.356, 0.662, 1.173 and 1.33 MeV, respectively.
An extensive investigation on gamma ray shielding features of Pd/Ag-based alloys
(Korean Nuclear Soc, 2019) Ağar, Osman; Sayyed, M., I; Akman, Erdi; Tekin, H. O.; Kacal, M. R.
A comprehensive study of photon interaction features has been made for some alloys containing Pd and Ag content to evaluate its possible use as alternative gamma radiations shielding material. The mass attenuation coefficient (mu/rho) of the present alloys was measured at various photon energies between 81 keV-1333 keV utilizing HPGe detector. The measured mu/rho values were compared to those of theoretical and computational (MCNPX code) results. The results exhibited that the mu/rho values of the studied alloys are in the same line with results of WinXCOM software and MCNPX code results at all energies. Moreover, Pd75/Ag25 alloy sample has the maximum radiation protection efficiency (about 53% at 81 keV) and lowest half value layer, which shows that Pd75/Ag25 has superior gamma radiation shielding performance among the other compared alloys. (C) 2018 Korean Nuclear Society, Published by Elsevier Korea LLC.
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., I
This 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.
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.
Gamma photon and neutron attenuation properties of MgO-BaO-B2O3-TeO2-Cr2O3 glasses: The role of TeO2
(Pergamon-Elsevier Science Ltd, 2019) Sayyed, M. I.; Tekin, H. O.; Ağar, Osman
This study focused on investigation of gamma photon and neutron shielding features of MgO-BaO-B2O3-TeO2-Cr2O3 glass system. The mass attenuation coefficients (MAC) have been calculated at different photon energies between 0.015 MeV and 10 MeV using MCNPX general-purpose of Monte Carlo code. The obtained mass attenuation coefficients have been utilized to evaluate several attenuation parameters such as half value layer (HVL), tenth value layer (TVL), mean free path (MFP) and effective atomic number (Z(eff)) through these values. Additionally, exposure buildup factor (EBF) values have been calculated using the G-P fitting approach. Moreover, variation of the shielding quantities has compared with commercial shielding glasses and some concretes. Additionally, the values of the macroscopic effective removal cross-section for fast neutron (Sigma(R)) have been determined. The results showed that sample encoded GS4 showed superior photon attenuation properties among the investigated samples while GS1 showed superior neutron attenuation.
An investigation on shielding properties of BaO, MoO3 and P2O5 based glasses using MCNPX code
(Elsevier Science Bv, 2019) Ağar, Osman; Sayyed, M. I.; Tekin, H. O.; Kaky, Kawa M.; Baki, S. O.; Kityk, I.
In the present work, some radiation shielding quantifies (mass attenuation coefficients, effective atomic number, effective electron density, half value layer and mean free path) for various BaO-MoO3-P2O5 ternary glass systems have been determined within the 0.015-15 MeV energy range, using WinXCom program. Additionally, the mass attenuation coefficients of all the investigated glasses have been calculated using MCNPX simulation code (version 2.6.0) and compared to those of WinXCom results. Among the studied glasses, BaMoP8 glass sample with MoO3 content of 70% mol is found to have superior gamma-ray shielding characteristics. Moreover, the glasses studied in this paper possess better radiation shielding properties by providing shorter half value layer (HVL) than RS-253 G18 commercial glass and some concrete samples namely ordinary, hematite-serpentine and ilmanite-limonite.
An investigation on shielding properties of different granite samples using MCNPX code
(Inst Materials Physics, 2018) Tekin, H. O.; Ergüzel, T. T.; Sayyed, M. I.; Singh, V. P.; Manici, T.; Altunsoy Güçlü, E. E.; Ağar, Osman
In this paper, mass attenuation coefficients of different granite samples are calculated at 662, 1173 and 1332 keV photon energies by using Monte Carlo code MCNPX (version 2.4.0). The obtained numerical results are compared not only with previous experimental and theoretical studies but also with standard theoretical data. The results showed that MCNPX results from generated simulation input agreed well with experimental studies and previous investigations. In addition, numerical deviation values of the mass attenuation coefficients in three photon energies has been obtained minimum between MCNPX andtheoretical data. The comaparative results underlined R-squared value for MCNPX approach out performs compared to both experiemental results and GATE model. Our results showed that, MCNPX is significantly convenient in comparison to GEANT4 for the energy range used. The results obtained from validated simulation input have been used for the calculation of some other important shielding parameter such as half value layer (HVL). It can be concluded that, standard simulation geometry would be useful for scientific community and MCNPX can be used as a powerful tool where no analogous experimental data exist for investigating shielding materials used in nuclear fields, industrial fields and high-energy radiation therapy facilities.
Photon and neutron shielding characteristics of samarium doped lead alumino borate glasses containing barium, lithium and zinc oxides determined at medical diagnostic energies
(Elsevier Science Bv, 2019) Almatari, M.; Ağar, Osman; Altunsoy Güçlü, E. E.; Kılıçoğlu, O.; Sayyed, M. I.; Tekin, H. O.
In the present work, we studied the radiation shielding parameters such as mass attenuation coefficients, effective atomic number, half value layer, mean free path, macroscopic effective removal cross-sections and neutron transmission function for samarium doped lead alumino borate glasses containing barium, lithium and zinc oxides at medical diagnostic energies (between 20 and 150 keV) using MCNPX code. The results showed that the photon attenuation depends on the type of modifier used (i.e. ZnO, BaO or Li2O) and also, upon the energy of the photon. The higher mass attenuation coefficients were found for the glass containing BaO. The results also revealed that the glass containing Li2O has the maximum effective atomic number between 20 and 40 keV. In addition, some important neutron shielding parameters such as macroscopic effective removal cross-sections (Sigma(R)) and neutron transmission function (N/N-0) have been calculated for investigated glass samples.
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.
Shielding features of concrete types containing sepiolite mineral: Comprehensive study on experimental, XCOM and MCNPX results
(Elsevier Science Bv, 2018) Sayyed, M. I.; Tekin, H. O.; Kılıçoğlu, O.; Ağar, Osman; Zaid, M. H. M.
Natural sepiolite mineral is a naturally occurring clay form belonging to a part of layered silicate. Because of its advantages such as low production cost, light-weight and convenient, it may be selected as an alternative shielding material to others. Radiation shielding performances of some concretes to sepiolite and B4C addictive have been researched reported in a wide energy region of 0.08-1.333 MeV using experimental data, MCNP and XCOM. The simulated data obtained by MCNPX are discussed and compared with the experimental results as well as with the XCOM results. The simulations match the experiments very well except for S3 sample. From the measurement, the maximum gamma-ray attenuation was detected in the concrete specimen with 10% sepiolite (S1) while the minimum attenuation of gamma-ray was noted in the concrete specimen with 30% sepiolite (S3). The addition of sepiolite mineral to concretes may be an alternative option that can be used in several radiation protection applications.
Synergistic effect of La2O3 on mass stopping power (MSP)/projected range (PR) and nuclear radiation shielding abilities of silicate glasses
(Elsevier, 2019) Kılıçoğlu, O.; Altunsoy Güçlü, E. E.; Ağar, Osman; Kamışlıoğlu, M.; Sayyed, M. I.; Tekin, H. O.; Tarhan, Nevzat
Photon and neutron attenuation properties of La2O3 based Li2O-SiO2-La2O3 glass system have been evaluated through MCNPX (2.6.0) Monte Carlo code at some photon energies of 0.256-1.33 MeV. In order to control the accuracy of the data, the estimated MCNPX of mass attenuation coefficients have been compared to those of WinXCOM software. The half value layer (HVL), tenth value layer (TVL) and mean free path (MFP) values of the selected glass system exhibited that the shielding performance of the gamma photons is related to the density of glass, thus, the inclusion of TeO2 to Li2O-SiO2 improves the capacity of the glass system to attenuate more photons. In addition, the effective removal cross-section (SR) calculations have been done. Further, Mass sopping power (MSP) and Projected range (PR) are calculated for proton particles (H-1) and alpha particles (He+2). It may be deduced that La4 glass among the studied samples may be kept in view as a superior glass in terms of shielding for photon and neutron while La0 glass can be considered as a best shielding material against to alpha and proton particles. The results of this study may be useful for shielding optimization of medical and industrial facilities.

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