Gamma Shielding Research Articles

Comparison of gamma and neutron shielding competences of Fe–Cu- and brass-added Portland cement pastes: an experimental and Monte Carlo study

In this study, Portland cement paste samples containing (Fe–Cu)x and brassx (where in x = 0, 5, 10, 15, 20%) were manufactured and some physical and nuclear shielding properties were determined. Experimental measurements for determining the mass attenuation coefficients (μ/ρ) of the cement samples were accomplished by utilizing 133Ba radioactive source with HPGe detector. In addition, gamma transmission factor and μ/ρ values were simulated with MCNPX codes and the experimental results were checked with MCNPX and theoretical WinXCOM results. The largest μ/ρ values were achieved by 20% Fe–Cu- and brass-added samples varying between 0.344–0.098 and 0.363–0.099 cm2/g for 0.081–0.383 photon energy ranges, respectively. To extensively evaluate the photon shielding competences of the cement samples, other vital parameters such as HVL, MFP, Zeff and Nel derived from μ/ρ values were also calculated. It is seen that the highest Zeffs were obtained for 20% brass- and Fe–Cu-added samples, whereas for MFP and HVL and Nel values, the least values were obtained. Additionally, to estimate the neutron shielding effectiveness of the cement samples, effective removal cross section (∑R) values were obtained. The ∑R values varied between 0.1123–0.1349 and 0.1065–0.1361 cm−1 for Fe–Cu- and brass-doped samples, respectively. The data obtained from the current study showed that adding Fe–Cu and brass improves the nuclear shielding properties of the produced cement samples.

Role of Bi2O3 in altering the structural, optical, mechanical, radiation shielding and thermoluminescence properties of heavy metal oxide borosilicate glasses

With the main intention of developing a transparent radiation shielding as well as a gamma dosimetric material, a series a heavy metal oxide borosilicate glass of composition (60-x) B2O3- 20SiO2- xBi2O3- 10ZnO- 10BaO with x = 0, 5, 10, 15 mol% was prepared by melt- quench technique. The glasses obtained were all transparent, except Bi-15 sample which is opaque and black in colour. The darkening is due to thermal reduction of Bi3+ ions, which is clearly indicated by absorption band around 377nm. XRD patterns showed the absence of crystalline peaks even in the opaque Bi-15 sample, confirming the glassy nature of all glasses. Furthermore, the structural changes in the glasses were confirmed with density measurement and FTIR studies. The Vickers hardness test done on transparent samples proved their higher mechanical strength, along with the theoretical calculation of elastic constants. The detailed analysis of gamma and neutron radiation shielding parameters for all the glasses was done using Photon Shielding and Dosimetry (PSD) software. The results suggested that the ϒ-ray shielding capacity increased, whereas the neutron attenuation ability decreased with the successive addition of Bi2O3. The opacity of Bi-15 can create problem in certain applications where transparency is needed. In order to assess the possibility of transparent glasses to be used as gamma dosimeter, they were irradiated with gamma rays of 1.25 MeV and thermoluminescence (TL) glow curves were recorded. An interesting behaviour of quenching of TL intensity for initial addition and enhancement of TL intensity for further addition of Bi2O3 was observed. The linearity of the dose- response curve for Bi-10 sample in two regions of gamma doses 100 Gy-3 kGy and 5- 50 kGy, showcased the chances of Bi-10 sample to be used as TL dosimeter for both low and high doses.

Gamma radiation shielding properties of poly (methyl methacrylate) / Bi2O3 composites

This work investigated the gamma-ray shielding performance, and the physical and mechanical properties of poly (methyl methacrylate) (PMMA) composites embedded with 0–44.0 wt% bismuth trioxide (Bi2O3) fabricated by the fast ultraviolet (UV) curing method. The results showed that the addition of Bi2O3 had significantly improved the gamma shielding ability of PMMA composites. Mass attenuation coefficient and half-value layer were examined using five gamma sources (Cs-137, Ba-133, Cd-109, Co-57, and Co-60). The high loading of Bi2O3 in the PMMA samples improved the micro-hardness to nearly seven times that of the pure PMMA. With these enhancements, it was demonstrated that PMMA/Bi2O3 composites are promising gamma shielding materials. Furthermore, the fast UV curing exerts its great potential in significantly shortening the production cycle of shielding material to enable rapid manufacturing.

Alkaline phosphate glasses and synergistic impact of germanium oxide (GeO2) additive: Mechanical and nuclear radiation shielding behaviors

In this study, mechanical and nuclear radiation shielding behaviors of highly efficient alkaline phosphate glasses with various GeO2 concentrations were evaluated for their nuclear radiation shielding applications. Moreover, the glass rigidity parameters of alkaline phosphate glasses were calculated for determination mechanical properties. The μm values were calculated using XCOM program and MCNPX simulation code. The nuclear radiation shielding properties (gamma and neutron) such as μm, HVL, TVL, MFP, Zeff, EBF, EABF, and ΣR were calculated for all alkaline phosphate glasses with various GeO2 concentrations. The results showed that μm, Zeff, and ΣR increased as the Bi2O3 concentration increased. The G14 glass sample had the minimum HVL, TVL, MFP, EBF and EABF. The G14 sample had the largest μm, Zeff, and the number of network bonds, and can be considered as an excellent attenuator for gamma and neutron shielding. The outcomes of recent investigation can be useful to understand the nature of GeO2 additive into alkaline phosphate glasses, which can be considered as a candidate shield type in medical and industrial radiation facilities.

Effect of Bi2O3 on mechanical features and radiation shielding properties of boro-tellurite glass system

This paper focuses on the effect of Bi2O3 content (up to 80 mol%) on mechanical features and radiation shielding characteristics of boro-tellurite glasses within TeO2–B2O3–Bi2O3 system. The basic mechanical parameters such as oxygen molar volume, packing density, hardness, and elastic moduli were studied based on Makishima–Mackenzie's theory. The shielding studies of the TeO2–B2O3–Bi2O3 glasses included gamma, electron and neutron radiations. The newly developed Phy-X/PSD program and Geant4 simulation were used to calculate the shielding parameters such as mass attenuation coefficient (μ/ρ), tenth value layer (TVL), mean free path (MFP), stopping power (ψe)), removal cross section (RCS), CSDA range, effective atomic number (Zeff), and half value layer (HVL). The concentration of Bi2O3 content had a significant effect on the gamma shielding competence of the investigated glasses. Form the results of gamma shielding studies, the highest μ/ρ (99.845 cm2/g) occurred at 0.015 MeV for TBB80 and the lowest μ/ρ (0.039 m2/g) occurred at 4 MeV for TBB40. The maximum values of Zeff for gamma interaction occurred at 0.02 MeV and they were 77.26, 78.81, 79.94, 80.80, and 81.48 for TBB40, TBB50, TBB50, TBB60, TBB70, and TBB80, respectively. The gamma shielding features of the investigated glasses were compared with those of various ordinary concretes, and Pb-free, Pb-based, and commercial glasses. The Bi2O3 content had also a considerable influence on the electron shielding competence of the tested glasses. The maximum values of Zeff for electron interaction occurred at 14 MeV and they were 44.58, 47.72, 50.41, 52.75, and 53.73 for TBB40, TBB50, TBB50, TBB60, TBB70, and TBB80, respectively. The results revealed that the bismuth boro-tellurite glasses could be useful for the shielding against gamma, electron, and neutron radiations, wherein the Bi2O3 content can be balanced according to the type and energy of radiation.

The impact of lead oxide on the optical and gamma shielding properties of barium borate glasses

In this study, the optical properties and gamma-ray competence of barium–lead borate glasses with chemical form BaO–B2O3–PbO have been investigated. The optical features such as optical energy gap (Eoptical), linear refractive index (n), molar refraction (Rmolar), molar polarizability (αmolar), metallization criterion (M), dielectric constants (static and optical), reflection loss (Rloss), optical transmission (Toptical) and others for the investigated glasses were calculated. Results show that Eoptical measures in (eV) and Eoptical values were changed from 3.18 to 2.53 eV, while n increases from 2.350 to 2.536. Phy-X/PSD software has been applied to report the radiation attenuation factors of the tested glasses. The results implied that all samples have the high attenuation ability at lower energies and the maximum µ/ρ is reported at 15 keV and lies within the range of 29.398 and 68.228 cm2/g. The minimum effective atomic number (Zeff) occurs at 1.5 MeV and equals to 10.90, 11.30, 12.41, 13.57, 16.79 and 20.55 for the tested glasses. At 0.2 MeV, the Zeff changes from 19.42 to 49.10 due to the increase of PbO from 0.5 to 30 wt%. The half value layer (HVL) results revealed that the current glasses have very low HVL values at the 15 keV (in the range of 0.00202 to 0.00671 cm). The HVL increases with the energy which indicates that the photon with high energy can penetrate the samples easily. The HVL results also showed that increasing the density of the samples leading to reduce the HVL and BBP30 has the thinner HVL, while BBP0.5 has the thicker HVL.

Relationship between melting-conditions and gamma shielding performance of fluoro-sulfo-phosphate (FPS) glass systems: A comparative investigation

To assess the relationship between gamma ray shielding performance and glass-melting conditions, an extensive investigation was performed on different types of fluoro-sulfo-phosphate (FPS) glasses. Four different FPS glasses melted in Al and Pt crucibles were modeled in MCNPX (version 2.6.0) general purpose Monte Carlo code. For this aim, a gamma-ray transmission setup has been modeled with essential simulation equipment. The mass attenuation coefficients for each glass sample in different melting-condition were determined. The obtained mass attenuation coefficients were utilized for determination of Half Value Layers (HVL) and mean free paths (mfp). Next, energy absorption buildup factors (EABF) and exposure buildup factors (EBF) of investigated FPS glasses were determined by using geometric-progression (G-P) fitting method. To evaluate the effect of glass-melting conditions on fast neutrons, effective removal cross sections of FPS glasses were calculated. Finally, an extensive comparison between the superior samples of FPS glasses melted in Al and Pt crucibles were performed. The results showed that GPT-4 sample melted in Pt crucible has relatively higher radiation shielding properties than GAL-2 sample which melted in Al crucible. In addition to material additive, the results showed that even glass-melting conditions has a significant impact on radiation shielding properties of glass material. It can be concluded that, in addition to the most effective material additives into glass structures to improve radiation shielding performances, providing them in the most favorable melting-conditions can provide a versatile improvement.

Gamma Shielding Properties of Erbium Zinc Tellurite Glass System Using Monte Carlo Method

Abstract This study aimed to determine the gamma shielding parameters of an Erbium Zinc Tellurite Glass System. The mass attenuation coefficients of Erbium Zinc Tellurite Glass System xEr2O3:20ZnO : (80-x) TeO2 were computed using Monte Carlo simulation at photon energies 20, 30, and 40 keV and 60, 356, 662, 1,173, 1,274, and 1,332 keV. The half-value layer thickness was calculated using the mass attenuation coefficients. The obtained results were compared to standard XCOM data and found comparable. It was found that the erbium zinc tellurite glass with a higher content of erbium is superior shielding material to other glasses. Thus, the validation of a generated Monte Carlo N-Particle Transport Code System-Extended simulation setup has been provided. It can be concluded that results of the present investigation would be very useful for applications of medical diagnostic and nuclear technology.

Assesment of the gamma and neutron shielding capabilities of the boro-tellurite glass quaternary containing heavy metal oxide using Geant4 and Phy-X/PSD database

This survey was conducted to reveal the gamma and neutron stopping performance of the 30PbO–10ZnO—(60-x)TeO2—xB2O3 (x = 0, 10, 20, 30, 50% mole) glass quaternary. Gamma and neutron attenuation parameters including the linear attenuation coefficient (μ), transmission fraction (TF), half value layer (HVL), mean free path (MFP), effective atomic number (Zeff), exposure buildup factor (EBF) and fast neutron removal cross-section (∑R) were determined computationally using the Geant4 and Phy-X/PSD database tools and for photon energies ranging between 0.284 MeV and 2.510 MeV. It was found that increasing the B2O3 content from 0% to 50% mole and correspondingly decreasing the TeO2 content from 60% to 10% mole results in a degradation of μ by 18.2% and of Zeff by 28.6% at 0.284 MeV. Due to this decrease in μ and Zeff, the values of TF and HVL increased by 37.3% and 22.4% respectively. In the present study it was also observed that the density (ρ) of glass quaternary decreased with the decreasing content of TeO2, and that the density of glass has a remarkable effect on the photon attenuation characteristics. The Degradation of μ, Zeff, ρ and the increase of TF and HVL proves that the photon attenuation ability of the glasses investigated worsens with decreasing content of TeO2, as Tellurium's atomic number and atomic mass are high compared to those of boron. While the decrease of TeO2 weakens the photon attenuation performance, it was found that fast neutron attenuation increases as ∑R increases from 0.108 to 0.116 for the glass specimens containing 60% and 10% mole of TeO2 respectively.

Evaluation of photon, neutron, and charged particle shielding competences of TeO2-B2O3-Bi2O3-TiO2 glasses

In this study, photon, neutron and charged particle shielding competences of five different glass systems which have the common chemical composition TeO2-B2O3-Bi2O3-TiO2 and contain different mole ratios of TeO2 in each sample were studied comprehensively. The fundamental photon shielding parameters, mass attenuation coefficient (µ/ρ), half value layer (HVL), mean free path (MFP), effective atomic number (Zeff), and electron density (Neff) were evaluated in the range of 0.015–20 MeV. The µ/ρ values of all investigated glasses were simulated by using Geant4 Monte Carlo simulation code. Besides, the simulation work was supported utilizing the web version of XCOM code and the outcomes from two methods were compared. A good agreement between two methods was observed. Results reveal that µ/ρ, MFP, HVL, Zeff and Neff parameters of the investigated glasses strongly depend on photon energy and chemical composition. Also, the energy absorption buildup factors (EABF) and exposure buildup factors (EBF) of the proposed glasses were calculated via G-P fitting parameters for photon energies in between 0.15 and 15 MeV. Results show that the greatest values of buildup factors take place at higher energies for all glasses. Finally, calculation of the fast neutron removal cross section (ΣR) values of the glasses were performed. According to our calculations, ΣR values vary between 0.1169 cm−1 for TBBT30 sample with TeO2 = 30 mol% (ρ = 6.39 g/cm3) and 0.1048 cm−1 for TBBT88 sample with TeO2 = 88 mol% (ρ = 5.39 g/cm3). Consequently, it can be said that the TBBT30 glass seems to be the most promising shield to be utilized for both gamma and neutron shielding implementations among investigated TBBT glasses.

Gamma shielding and compressive strength analyses of polyester composites reinforced with zinc: an experiment, theoretical, and simulation based study

The preparation of materials with high attenuation performance is one of the major issues in the radiation shielding applications. This study is based on the investigation of gamma-shielding performances of various polyester composites reinforced with Zn. Utilizing gamma spectrometer based on HPGe detector, the mass attenuation coefficient (μ/ρ) of the present composites was measured at various photon energies between 59.5–1408 keV. The obtained experimental data were confirmed with those of MCNPX code as well as XCOM program. It is found that the attenuation coefficient values of the studied composites are in good agreement with the results of other approaches at the investigated energies. The best photon-shielding effectiveness was observed in the composite tagged with Zn (10%). The shielding characteristics of composite enhances with the addition of Zn as filler.

Radiation shielding properties of bismuth borate glasses doped with different concentrations of cadmium oxides

The current study is aimed to investigate the gamma ray and neutron shielding properties of the bismuth borate glass system with various concentration of cadmium oxide (0, 5, 10 and 15 mol%). The XRD spectra confirms the amorphous state of the prepared samples. A number of physical and mechanical properties (molar volume, oxygen molar volume, oxygen packing density, Poisson’s ratio, optical absorption and dissolution rates) have been determined. The mass attenuation coefficients were estimated at different energy levels by using XCOM and EXABcal programs. The gamma and neutron beam shielding properties are evaluated through the calculation of several parameters such as equivalent number, specific gamma ray constant, gamma dose rate, specific absorbed fraction of energy and total neutron removal cross-section. Comparing with the standard gamma ray shielding materials, the new composition exhibits promising properties in terms of mass attenuation, halve value layer and mean free path. The glass with the highest concentration of CdO was found to be good shielding material for neutrons compared with some standard shielding materials (water, graphite, ordinary concrete and hematite-serpentine concrete).

McStas and Scatter Logger driven calculations of prompt gamma shielding for neutron guides

McStas ScatterLogger component bundle was adapted for evaluating a contribution to dose rate around neutron guides arising from prompt gamma radiation accompanying neutron capture in the supermirror guide coating upon specular reflection. Thickness o

Structural, mechanical and radiation shielding properties of newly developed tungsten lithium borate glasses: An experimental study

The melt quench technique was used to fabricate the (25-x)Li2O-75B2O3-xWO3 (x = 1, 3, 5 and 7.5 mol%). The mass attenuation coefficients (μm) of the studied glasses were obtained by using the Gamma (γ) rays spectrometer (CANBERRA photo multiplier tube base model 802) which includes a detector (3 × 3 in.) NaI(Tl) crystal and the multichannel analyzer. The measured values have been compared with XCOM program at selected photon energies. Geometric progression (G–P) fitting method has been used to calculate the exposure build-up factor (EBF) and energy absorption build-up factor (EABF) in the energy range of 0.015–15 MeV. Moreover, EBF and EABF values have been applied to compute the specific fraction of absorbed energy (Sfae) and relative dose distribution (Rdd). The pulse-echo technique has been used to measure the elastic moduli for glass samples. The TBL4 glass sample shows the highest μm, effective atomic number (Zeff) and Young moduli values and lowest half value layer (HVL), mean free path (MFP), EBF, EABF, Sfae and Rdd values. The results of this investigations revealed that the fabricated TBL4 glass sample could be potentially utilized as an efficient and desirable kind of glass material as gamma shield to reduce the deleterious effects of radiation.

Comparative evaluation of nuclear radiation shielding properties of xTeO2 + (100–x)Li2O glass system

In the present investigation, nuclear radiation shielding parameters of xTeO2 + (100–x)Li2O (where x = 95, 90, 85, 80, 75, and 70 mol%) glass system have been examined. Gamma shielding parameters such as mass attenuation coefficients (MAC), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), effective atomic number (Zeff), effective electron density (Neff) were calculated. Moreover, neutron effective cross sections (∑R) are determined. The calculations for present materials have been performed in different photon energy ranges (0.01–20 MeV) and using Monte Carlo N-Particle eXtended (MCNPX) simulation code and theoretical results were also obtained with WinXcom program. The results obtained from the MCNPX and WinXcom program were found to be in well harmony. Moreover, for the assessment of radiation shielding success of tellurite glasses, the mass stopping power (MSP) and projected range (PR) were computed for proton and alpha particles using stopping and range of ions in matter (SRIM) code. When the results obtained from the study are examined, it is seen that 95TeLi glass has the lowest HVL, TVL, MFP, TF and the highest (∑R) values. Therefore, the 95TeLi glass has the most perfect radiation shielding achievement than other investigated glasses.

Gamma, X-ray and neutron shielding properties of boron polymers

We have studied the X-ray and gamma radiation shielding parameters such as mass attenuation coefficient, linear attenuation coefficient, Half Value Layer (HVL), Tenth Value Layer (TVL), effective atomic number and electron density in some boron polymers of different boron based polymers [ Polymer A-PolyBorazylene (B 3 N 3 H 4 ), Polymer B- 4-Vinylphenyl Boronic acid (C 8 H 9 O 2 B), Polymer C- Borazine (B 3 N 3 H 6 ), Polymer D- 3-Acrylamidophenylboronic acid (C 9 H 10 BNO 3 ) Polymer E-Phenylethenylboronic acid (C 14 H 19 BO 2 ), Polymer F- 4-Aminophenylboronic acid (C 12 H 18 BNO 2 ) and Polymer G- 3- Aminophenylboronic acid (C 6 H 8 BNO 2 )]. We have also studied the neutron shielding properties such as coherent neutron scattering length, incoherent neutron scattering lengths, coherent neutron scattering cross section, incoherent neutron scattering cross sections, total neutron scattering cross section and neutron absorption cross sections in the boron polymers. We have compared the shielding properties among the studied different boron polymers. From the detail study, it is clear that the boron polymer Phenylethenylboronic acid is good absorber for X-ray, gamma radiation and neutron. Hence, we suggest that the boron polymer Phenylethenylboronic acid is good shielding material for X-ray, gamma and neutrons.

Radiation shielding structures : Concepts, behaviour and the role of the heavy weight concrete as a shielding material - Rewiev

The construction of radiation shielding buildings still developed. Application of ionizing radiations became necessary for different reasons, like electricity generation, industry, medical (therapy treatment), agriculture, and scientific research. Different countries all over the world moving toward energy saving, besides growing the demand for using radiation in several aspects. Nuclear power plants, healthcare buildings, industrial buildings, and aerospace are the main neutrons and gamma shielding buildings. Special design and building materials are required to enhance safety and reduce the risk of radiation emission. Radiation shielding, strength, fire resistance, and durability are the most important properties, cost-effective and environmentally friendly are coming next. Heavy-weight concrete (HWC) is used widely in neutron shielding materials due to its cost-effectiveness and worthy physical and mechanical properties. This paper aims to give an overview of nuclear buildings, their application, and behaviour under different radiations. Also to review the heavy-weight concrete and heavy aggregate and their important role in developing the neutrons shielding materials. Conclusions showed there are still some gaps in improving the heavy-weight concrete (HWC) properties.

Influence of ZrO2 on gamma shielding properties of lead borate glasses

In this paper, new lead borate glass system in the chemical form of 40B2O3–40PbO–20Li2O3–xZrO2; where x = 0, 0.25, 0.50, 1, and 1.5 mol% has been synthesized. Gamma-ray shielding properties of these glasses have been tested in terms of mass attenuation coefficient (μ/ρ), half value layer (HVL), effective atomic number (Zeff), mean free path (MFP), and exposure build-up factor (EBF). The μ/ρ values of the prepared glasses were generated by FLUKA Monte Carlo simulations over an extended energy range of 0.015–15 MeV, and then, the generated data were verified using the calculated values of XCOM software. The results showed that gamma-ray shielding ability of BPLZ0.00 is superior among the other prepared glasses. Moreover, the gamma-ray shielding properties of the current glass system have been compared with that of some commercial glasses and newly developed HMO glasses. It can be concluded that the prepared glass system could be useful to design and/or develop novel shields for radiation protection applications.

Evaluation of the radiation shielding capabilities of the Na2B4O7–SiO2–MoO3-Dy2O3 glass quaternary using Geant4 simulation code and Phy-X/PSD database

The important gamma and neutron radiation shielding parameters of the Dy3+ doped (65-x)Na2B4O7–15SiO2–20MoO3-xDy2O3 (x = 0, 5, 10, 15, 20 mol%) glass quaternary system were investigated to provide decisive information for their application in radiation environment. Gamma and neutron attenuation properties of the glass systems studied here were evaluated in terms of the mass attenuation coefficient (μm), transmission fraction (TF), half value layer (HVL), mean free path (MFP), effective atomic number (Zeff), exposure buildup factors (EBF) and fast neutron removal cross-section (∑R) parameters. Investigation of the each aforementioned parameter was performed thanks to the utilization of Monte Carlo simulations along with the Phy-X/PSD database. The photon attenuation characteristics were evaluated for gamma ray energies varying between 0.284 and 5.0 MeV. This study indicated that increase of the Dy2O3 content from 0% to 20% mole, enhances the gamma shielding capability due to the increase of the parameters μm and Zeff. In this study it was also observed that ∑R increases from 0.099 to 0.107 cm−1 as the molar fraction of Dy2O3 increases.

Theoretical and experimental validation gamma shielding properties of B2O3–ZnO–MgO–Bi2O3 glass system

In the present work, we fabricated a series of six glasses to be utilized in the field of radiation shielding application. Glasses have been synthesized using a melt-quenching ordinary technique. In this work, we investigated the structural properties of these glasses using Raman spectroscopy. Moreover, optical properties have been studied in the present work. The radiation attenuation ability for the present samples was also investigated and measured using transmission geometry between 81 and 964.1 keV. The mass attenuation coefficient was measured and the results were validated by the WinXcom program. Also, radiation protection efficiency (RPE) was evaluated and discussed in terms of photon energy and Bi2O3 concentration. From RPE curve, we found that the fabricated glasses can be used as effective shielding materials especially for the low energies (81–383 keV). The half value layer also was calculated and the results of this parameter showed that S6 (contains 60 mol% of Bi2O3) has the higher probability of the interaction with gamma photons, leading to less number of photons transmitted this sample and thus better photon attenuator.