scholarly journals Study of Gamma Ray Exposure Buildup Factor for Some Ceramics with Photon Energy, Penetration Depth and Chemical Composition

2013 ◽  
Vol 2013 ◽  
pp. 1-6 ◽  
Author(s):  
Tejbir Singh ◽  
Gurpreet Kaur ◽  
Parjit S. Singh
Keyword(s):  
Silicon Carbide ◽  
Chemical Composition ◽  
Penetration Depth ◽  
Photon Energy ◽  
Gamma Ray ◽  
Magnesium Diboride ◽  
Mean Free Path ◽  
Buildup Factor ◽  
Fitting Method ◽  
Buildup Factors

Gamma ray exposure buildup factor for some ceramics such as boron nitride (BN), magnesium diboride (MgB2), silicon carbide (SiC), titanium carbide (TiC) and ferrite (Fe3O4) has been computed using five parametric geometric progression (G.P.) fitting method in the energy range of 0.015 to 15.0 MeV, up to the penetration of 40 mean free path (mfp). The variation of exposure buildup factors for all the selected ceramics with incident photon energy, penetration depth, and chemical composition has been studied.

scholarly journals A Systematical Characterization of TeO2–V2O5 Glass System Using Boron (III) Oxide and Neodymium (III) Oxide Substitution: Resistance Behaviors against Ionizing Radiation

2021 ◽  
Vol 11 (7) ◽  
pp. 3035
Author(s):  
H. O. Tekin ◽  
Shams A. M. Issa ◽  
G. Kilic ◽  
Hesham M. H. Zakaly ◽  
N. Tarhan ◽  
...  
Keyword(s):  
Gamma Ray ◽  
Effective Atomic Number ◽  
Mean Free Path ◽  
Radiation Shielding ◽  
Glass System ◽  
Buildup Factor ◽  
Attenuation Coefficients ◽  
Gamma Ray Attenuation ◽  
Buildup Factors

This study aimed to perform an extensive characterization of a 74.75TeO2–0.25V2O5–(25 − x)B2O3-xNd2O3 glass system with (x = 0, 0.5, 1.0, and 1.5 mol%) for radiation shielding properties. Linear and mass attenuation coefficients were determined using Phy-X PSD software and compared with the simulation using Monte Carlo software MCNPX (version 2.7.0). Half value layer, mean free path, tenth value layer, effective atomic number, exposure buildup factor, and energy absorption buildup factors of VTBNd0.0, VTBNd0.5, VTBNd1.0, and VTBNd1.5 glasses were determined, respectively. The results showed that boron (III) oxide and neodymium (III) oxide substitution has an obvious impact on the gamma ray attenuation properties of the studied glasses. It can be concluded that the VTBNd1.5 sample with the highest content of neodymium (III) oxide (1.5 mol%) is the superior sample for shielding of gamma radiation in the investigated energy range.

scholarly journals Enhancement of Bentonite Materials with Cement for Gamma-Ray Shielding Capability

Materials ◽  
2021 ◽  
Vol 14 (16) ◽  
pp. 4697
Author(s):  
Ahmed M. El-Khatib ◽  
Mohamed Elsafi ◽  
Mohamed N. Almutiri ◽  
R. M. M. Mahmoud ◽  
Jamila S. Alzahrani ◽  
...  
Keyword(s):  
Gamma Ray ◽  
Mean Free Path ◽  
Radiation Shielding ◽  
Point Sources ◽  
Linear Attenuation Coefficient ◽  
Buildup Factor ◽  
Chemical Compositions ◽  
Attenuation Coefficients ◽  
Water Holding ◽  
Mixed Samples

The gamma-ray shielding ability of various Bentonite–Cement mixed materials from northeast Egypt have been examined by determining their theoretical and experimental mass attenuation coefficients, μm (cm2g−1), at photon energies of 59.6, 121.78, 344.28, 661.66, 964.13, 1173.23, 1332.5 and 1408.01 keV emitted from 241Am, 137Cs, 152Eu and 60Co point sources. The μm was theoretically calculated using the chemical compositions obtained by Energy Dispersive X-ray Analysis (EDX), while a NaI (Tl) scintillation detector was used to experimentally determine the μm (cm2g−1) of the mixed samples. The theoretical values are in acceptable agreement with the experimental calculations of the XCom software. The linear attenuation coefficient (μ), mean free path (MFP), half-value layer (HVL) and the exposure buildup factor (EBF) were also calculated by knowing the μm values of the examined samples. The gamma-radiation shielding ability of the selected Bentonite–Cement mixed samples have been studied against other puplished shielding materials. Knowledge of various factors such as thermo-chemical stability, availability and water holding capacity of the bentonite–cement mixed samples can be analyzed to determine the effectiveness of the materials to shield gamma rays.

scholarly journals Tailoring bismuth borate glasses by incorporating PbO/GeO2 for protection against nuclear radiation

2021 ◽  
Vol 11 (1) ◽  
Author(s):  
Ashok Kumar ◽  
Anisha Jain ◽  
M. I. Sayyed ◽  
Farah Laariedh ◽  
K. A. Mahmoud ◽  
...  
Keyword(s):  
Radiation Protection ◽  
Photon Energy ◽  
Effective Atomic Number ◽  
Mean Free Path ◽  
Radiation Shielding ◽  
Nuclear Radiation ◽  
Neutron Shielding ◽  
Bismuth Borate ◽  
Removal Cross Section ◽  
Buildup Factors

AbstractNuclear radiation shielding capabilities for a glass series 20Bi2O3 − xPbO − (80 − 2x)B2O3 − xGeO2 (where x = 5, 10, 20, and 30 mol%) have been investigated using the Phy-X/PSD software and Monte Carlo N-Particle transport code. The mass attenuation coefficients (μm) of selected samples have been estimated through XCOM dependent Phy-X/PSD program and MCNP-5 code in the photon-energy range 0.015–15 MeV. So obtained μm values are used to calculate other γ-ray shielding parameters such as half-value layer (HVL), mean-free-path (MFP), etc. The calculated μm values were found to be 71.20 cm2/g, 76.03 cm2/g, 84.24 cm2/g, and 90.94 cm2/g for four glasses S1 to S4, respectively. The effective atomic number (Zeff)values vary between 69.87 and 17.11 for S1 or 75.66 and 29.11 for S4 over 0.05–15 MeV of photon-energy. Sample S4, which has a larger PbO/GeO2 of 30 mol% in the bismuth-borate glass, possesses the lowest MFP and HVL, providing higher radiation protection efficiency compared to all other combinations. It shows outperformance while compared the calculated parameters (HVL and MFP) with the commercial shielding glasses, different alloys, polymers, standard shielding concretes, and ceramics. Geometric Progression (G-P) was applied for evaluating the energy absorption and exposure buildup factors at energies 0.015–15 MeV with penetration depths up to 40 mfp. The buildup factors showed dependence on the MFP and photon-energy as well. The studied samples' neutron shielding behavior was also evaluated by calculating the fast neutron removal cross-section (ΣR), i.e. found to be 0.139 cm−1 for S1, 0.133 cm−1 for S2, 0.128 cm−1 for S3, and 0.12 cm−1 for S4. The results reveal a great potential for using a glass composite sample S4 in radiation protection applications.

scholarly journals Trivalent Ions and Their Impacts on Effective Conductivity at 300 K and Radio-Protective Behaviors of Bismo-Borate Glasses: A Comparative Investigation for Al, Y, Nd, Sm, Eu

Materials ◽  
2021 ◽  
Vol 14 (19) ◽  
pp. 5894
Author(s):  
Ghada ALMisned ◽  
Huseyin O. Tekin ◽  
Ghaida Bilal ◽  
Antoaneta Ene ◽  
Gokhan Kilic ◽  
...  
Keyword(s):  
Energy Range ◽  
Photon Energy ◽  
Gamma Ray ◽  
Glass Composition ◽  
Effective Conductivity ◽  
Atomic Weight ◽  
Comparative Investigation ◽  
Borate Glasses ◽  
Shielding Properties ◽  
Buildup Factors

We aimed to determine the contribution of various trivalent ions like Al and rare-earths (Y, Nd, Sm, Eu) on resistance behaviors of different types of bismo-borate glasses. Accordingly, eight different bismuth borate glasses from the system: 40Bi2O3–59B2O3–1Tv2O3 (where Tv = Al, Y, Nd, Sm, and Eu) and three glasses of (40Bi2O3–60B2O3; 37.5Bi2O3–62.5B2O3; and 38Bi2O3–60B2O3–2Al2O3) compositions were extensively investigated in terms of their nuclear attenuation shielding properties, along with effective conductivity and buildup factors. The Py-MLBUF online platform was also utilized for determination of some essential parameters. Next, attenuation coefficients, along with half and tenth value layers, have been determined in the 0.015 MeV–15 MeV photon energy range. Moreover, effective atomic numbers and effective atomic weight, along with exposure and energy absorption buildup factors, were determined in the same energy range. The result showed that the type of trivalent ion has a direct effect on behaviors of bismo-borate glasses against ionizing gamma-rays. As incident photon energy increases, the effective thermal conductivity decreases rapidly, especially in the low energy range, where photoelectric effects dominate the photon–matter interaction. Sample 8 had the minimum heat conductivity at low photon energies; our findings showed that Eu-reinforced bismo-borate glass composition, namely 40Bi2O3–59B2O3–1Eu2O3, with a glass density of 6.328 g/cm3 had superior gamma-ray attenuation properties. These outcomes would be useful for the scientific community to observe the most suitable additive rareearth type and related glass composition for providing the aforementioned shielding properties, in terms of needs and utilization requirements.

Development of Buildup Factors for Updating the ANSI/ANS-6.4.3 Standard

2010 ◽  
Author(s):  
Charlotta E. Sanders
Keyword(s):  
Energy Absorption ◽  
Gamma Ray ◽  
Radiation Transport ◽  
Buildup Factor ◽  
Mass Energy ◽  
Attenuation Coefficients ◽  
One Dimensional ◽  
Section Data ◽  
Transport Code ◽  
Buildup Factors

The ANSI/ANS-6.4.3-1991 Standard, Gamma-Ray Attenuation Coefficients and Buildup Factors for Engineering Materials, is currently being updated by an American Nuclear Society (ANS) Working Group. The ANSI/ANS-6.4.3, 1991 standard, which is “withdrawn” due to the failure to meet the requirement of the ANS to have standards updated every ten years, contains buildup factor values that are derived from data that is over seventeen years old. In addition, computer technology has significantly improved since 1991, allowing for more complicated, computationally demanding codes to be utilized. Therefore, the ANSI/ANS-6.4.3-1991 standard is being re-visited to include updated data and to include modern codes. Gamma-ray buildup factors and attenuation coefficients are being generated for common shielding materials (e.g., concrete, steel, water, etc.) utilizing the ENDF/B-VI.8 cross-section data library, which is distributed by Brookhaven National Laboratory’s National Nuclear Data Center (NNDC). One modern code, Monte Carlo N-Particle (MCNP5/MCNPX), is being compared with PALLAS-1D (VII) and Anisotropic Source-Flux Iteration Technique (ASFIT-VARI), which were used to develop values included in ANSI/ANS-6.4.3-1991. PALLAS-1D (VII) is a code for direct integration of transport equation in one-dimensional plane and spherical geometries while ASFIT-VARI is a gamma-ray transport code system for one-dimensional finite systems. MCNP5 is a general purpose Monte Carlo radiation transport code that tracks particles (e.g., neutron and photons) at numerous energies in a three dimensional configuration of materials. The MCNP5 radiation transport code require response function input to provide dose and exposure output. Mass energy-absorption coefficients and mass energy-transfer coefficients are required to develop absorbed dose and exposure responses. The National Institute of Standards and Technology (NIST) provide and maintain the most up-to-date mass energy-absorption coefficient and mass energy-transfer coefficient database currently available. The NIST values are used in these initial buildup factor calculations to prove the validity of the methodology used and allow for preliminary comparisons. The energy absorption (dose in material) and exposure buildup factors are calculated at mfp values of interest, consistent with ANSI/ANS-6.4.3-1991 up to forty mfp. Comparisons between the new buildup factors and the previous results presented in the ANSI/ANS-6.4.3-1991 standard indicate that there is fairly good agreement. Differences in buildup factor values can be attributed to differences in cross-section data libraries, numerical methods, and physics treatments within the respective codes.

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