Neutron Removal Cross Sections Research Articles

On the use of green concrete composite as a nuclear radiation shielding material

In the present study, the samples of sustainable green concrete composites reinforced with hematite were prepared by partially replacing Ordinary Portland Cement (OPC) with flyash. The mechanical and gamma radiation shielding parameters have been measured experimentally for these prepared concrete composites. The experimental measurements were performed by using narrow beam transmission geometry (total scatter acceptance angle (θsc) = 1.78°) with NaI(Tl) spectroscopy in the gamma photon energy range of 59.54 keV–1332 keV. These experimentally measured values of linear attenuation coefficient are further used to calculate the values of half value layer, mass attenuation coefficient, effective atomic number, electron density, exposure build up factor, Klein-Nishina electronic, electron transfer and Compton mass attenuation coefficients. The fast neutron removal cross sections (∑R cm−1) were calculated for the concrete samples under investigations. The experimental values of mass attenuation coefficient have been compared with the results of theoretical values obtained by using winXCOM computer software and FLUKA simulations code. Excellent agreements have been observed between experimental, theoretical and simulation results.

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

Nuclear 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.

Responsibility of Bi2O3 Content in Photon, Alpha, Proton, Fast and Thermal Neutron Shielding Capacity and Elastic Moduli of ZnO/B2O3/Bi2O3 Glasses

The effect of Bi2O3 content on photon, alpha particle, proton, fast and thermal neutron shielding capacity, and elastic moduli of 10ZnO-(90-x)B2O3-xBi2O3 (ZBB-glasses): x = 25–50 mol% has been investigated. The mass density and Bi-content of the ZBB-glasses had the greatest impact on the values of mass and linear attenuation coefficients. The mass and linear attenuation coefficients values were followed the trend (ZBB25)MAC,LAC < (ZBB30) MAC,LAC < (ZBB35) MAC,LAC < (ZBB40) MAC,LAC < (ZBB45) MAC,LAC < (ZBB50) MAC,LAC. The mean free path (MFP) and half value layer (HVL) were having the same trend and opposite to which obtained in mass and linear attenuation coefficients. All the ZBB-glasses showed almost similar charged particle shielding capacity. However, ZBB50 had a comparable charged particle absorption efficiency. There was a 57% growth in fast neutron removal cross section as Bi2O3 molar concentration increased to 50% in the ZBB-glass matrix. ZBB50 possesses the highest fast neutron removal cross section among the ZBB-glasses. In terms of thermal neutron absorbing capacity, the presence of B in the glass matrix ensures that the ZBB-glasses are good thermal neutron absorption. ZBB25 has the highest thermal neutron absorption capacity among the investigated glasses. Generally, ZBB-glasses can be adopted for photon, thermal neutron, proton, and alpha particle shielding purposes. In addition, elastic (shear, longitudinal, and Young’s) moduli and Poisson’s ratio are changed significantly with the increase of Bi2O3 content mol% in ZBB-glasses.

Gamma-ray interactions with ytterbium ions doped BLFB glasses for shielding applications

The ytterbium (Yb3+) ions doped barium lithium fluoroborate (BLFB) glasses have been prepared with conventional melt quenching method and explored for nuclear radiation (γ-ray) shielding applications. The XRD analysis confirms the aperiodic nature of the glasses. The glass density was increased from 2.84 to 4.87 (gm/cm3) with the increase of Yb3+ content. The refractive index (n) increased from 1.544 to 1.599 while the molar volume (Vm) decreased from 27.656 to 17.458 (gm/cm−3) for 0.05YbBLFB to 2YbBLFB glasses. The optical packing density (OPD) increased from 9.943 to 15.751 (mol/cm3) while the electronic polarizability (αe) varied from 346.23 to 5.913 (10–22 cm3) for all glasses due to the increase of Yb3+ ions’ concentration. By employing the Phy-X/PSD program, γ-ray attenuation parameters such as linear attenuation coefficient (μ), mass attenuation coefficient (μ/ρ), effective atomic number (Zeff), effective electron density (Neff), half value layer (HVL), tenth value layer (TVL), and mean free path (MFP) were evaluated within the γ-ray energy range of 15 KeV–15 MeV. In addition, the geometric progression (G‒P) fitting method is used to investigate the exposure and energy absorption buildup factors (EBF and EABF) with discrete penetration depths (1–40 mfp) of all glasses. Also, the fast neutron removal cross-section (FNRCS) parameter is also estimated for all glasses. Therefore, among all the glasses, 2YbBLFB glass possesses higher μ/ρ, Zeff, Neff, Zeq values and lower HVL, TVL, and MFP values. And this glass is suggested for the best gamma-ray shielding applications.

In-depth survey of nuclear radiation attenuation efficacies for high density bismuth lead borate glass system

MCNPX, Geant4 and FLUKA codes are employed to compute mass attenuation coefficients (μ/ρ) for 20Bi2O3-(80-x)B2O3-xPbO (x = 0, 20, 30, 40 and 60 mol%) glasses at 20, 30, 40 and 60 KeV, 133Ba (81, 161, 223, 276, 303, 356 and 384 keV), 57Co (122 and 136 KeV), 22Na (511 and 1275 keV),137Cs (662 keV),54Mn (835 keV), 60Co (1173 and 1333 keV) and 42K (1524 keV) photon peaks where 20, 30, 40 and 60 KeV energies are utilized for Mammography, Dental, General and Computed tomography (CT) scanning accordingly, in this study. All simulated μ/ρ outcomes accuracy was verified by WinXCOM and Phy-X/PSD programs’ μ/ρ findings and we noticed a satisfactory agreement among them. From μ/ρ and linear attenuation coefficient (μ) values effective atomic number (Zeff), effective electron density (Neff), half-value layer (HVL), tenth-value layer (TVL) and mean free path (MFP) have been determined. 20Bi2O3-20B2O3-60PbO (mol%) glass HVL and MFP have been compared with some commercial glasses, alloys, polymers, concretes and lead and ceramics corresponding values. Later equivalent atomic numbers (Zeq) and applying geometric progression (G–P) fitting method at 1 – 40 mfp penetration depths (PDs) at 0.015–15 MeV energy range exposure buildup factors (EBFs) and energy absorption buildup factors (EABFs) were estimated. At all selected twenty energies derived radiation protection efficiency (RPE) results confirmed studied samples’ excellent efficacy for low energy photons absorption. Moreover, applying SRIM codes mass stopping powers (MSPs) and projected ranges (PRs) for protons and α-particles and utilizing ESTAR database electron MSPs and continuous slowing down approximation (CSDA) range for electrons were determined at kinetic energy (KE) range of 0.015–15 MeV. Further fast neutron removal cross-sections (ΣR), for 0.0253 eV energy neutrons coherent and incoherent scattering cross-sections (σcs and σics), absorption cross-section (σA) and total cross-section (σT) quantities were evaluated. Derived ΣR was changed at 0.1166–0.123 cm−1 range depending on PbO addition in chosen samples. 20Bi2O3-80B2O3 (mol%) glass has larger σT (23.094 cm−1) in all studied samples for thermal neutron absorption while 20Bi2O3-20B2O3-60PbO (mol%) sample shows superior attenuation factors for photons and fast neutrons signifying included PbO positive effect.

Gamma-Ray and Fast Neutron Shielding Parameters of Two New Titanium-Based Bulk Metallic Glasses

Introduction: Low-density bulk metallic glass (BMG) with good structural characteristics has the potential of being used for structural radiation shielding purposes. This study was conducted on two new low-density titanium (Ti)-based BMGs (i.e., Ti32.8Zr30.2Ni5.3Cu9Be22.7 and Ti31.9Zr33.4Fe4Cu8.7Be22) to investigate their photon and fast neutron shielding capacities. Material and Methods: The mass attenuation coefficients, half-value layers, effective atomic numbers, and exposure buildup factors of the two BMGs were calculated at the photon energy values of 15 keV and 15 MeV. Computation of mass attenuation coefficients and effective atomic numbers was accomplished using the XCOM and auto-Zeff software, respectively. In addition, the geometric progression procedure-based computer code EXABCal was used for calculating the exposure buildup factors of BMG. The fast neutron removal cross-sections were also calculated for the two BMGs. The calculated photon and fast neutron shielding parameters for BMGs were compared with those of lead (Pb), heavy concrete, and some recently developed glass shielding materials and then analyzed according to their elemental compositions. Results: The results showed that though Pb had a better photon shielding capacity, Ti-BMG attenuated photons better than heavy concrete. Furthermore, BMG had a higher neutron removal cross-section, compared to heavy concrete and some recently developed glass shielding materials. The neutron removal cross-sections of Ti32.8Zr30.2Ni5.3Cu9Be22.7 and Ti31.9Zr33.4Fe4Cu8.7Be22 were obtained as 0.1663 and 0.1645 cm-1,respectively. Conclusion: his study revealed that Ti-based BMG with high strength and low density have potential applications in high-radiation environments, particularly in nuclear engineering for source and structural shielding.

Multiple characterization of some glassy-alloys as photon and neutron shields: In-silico Monte Carlo investigation

In the present work, the nuclear radiation shielding proficiency of eight glassy alloys (Gd25RE25Co25Al25 (RE = Tb, Dy and Ho)) containing different amounts of rare earth elements was investigated with MCNPX simulation codes. Mass attenuation coefficients (μ/ρ) of the glassy alloys were simulated in the energy interval of 0.2–20 MeV by exploiting MCNPX codes, and the generated data were found to match with theoretical WinXCOM results. Next, other crucial photon attenuation parameters, effective atomic number (Zeff), Half Value Layer (HVL), and Mean Free Path (MFP), were gotten out using μ/ρ values. It was seen that Er20Tm20 and Er20Tb20 samples replaced with Er by Gd had the highest Zeff and μ/ρ values, whereas HVL and MFP values were the smallest among the other glassy alloys. Geometric progression (GP) procedure was enjoyed to achieve the exposure and energy absorption buildup factors (EBF and EABF) for the glassy alloys proposed. EABFs and EBFs took the largest and lowest values for Gd25Tb25 and Er20Tm20, respectively, to the other samples. Furthermore, the glassy alloys’ neutron reduction abilities were estimated by acquiring fast neutron removal cross-sections (∑R). It was noticed that the ∑R values of the glassy alloys are increased with the rising sample density and seen to be comparable to ∑R values of water and ordinary concrete. The results obtained from this study are important in that they show that glassy alloys can be used as radiation shielding.

Photoluminescence and gamma ray shielding properties of novel Dy3+: GSBS glass for solid state W-LEDs and radiation applications

A novel dysprosium doped gadolinium strontium borosilicate (Dy3+: GSBS) glass with luminescence and radiation shielding properties was prepared with conventional melt quenching method, of which composition was [(55-x) H3BO3 + 15 SiO2 + 5 Gd2O3 + 10 SrCO3 + 10 CdF2 + 5 TiO2 + x Dy2O3 (where x = 0.05, 0.3, 0.5, 1, 2 and 3 in wt. %, hereafter refers to as Dy3+ ions concentration)]. And it was characterized through X-ray diffraction (XRD), visible absorption, excitation, photoluminescence, decay time measurements and Phy-X/PSD program. Its aperiodic nature was confirmed by XRD patterns. The density and refractive index increase with the increase of Dy3+ ions concentration. The optical basicity (Ʌth), the optical packing density, the average molecular weight (g), the optical electro-negativity (χ), the boron-boron distance (dB-dB) and the steepness parameter (S) were measured. The Nephelauxetic ratio (β) and the bonding parameter (δ) reveal that the (Dy–O) glass are covalent in nature. The oscillator strength and Judd-Ofelt (J-O) intensity parameters were calculated and then were used to predict some radiative properties, such as the transition probability (A), the stimulated emission cross-section (σPE) and the branching ratios (βR) for each glass. The colour coordinates (x, y) and (u, v), the colour purity (CP), the colour correlated temperature (CCT), and the yellow to blue ratio (Y/B) were also articulated. The prepared glasses are positioned in the white region of the CIE diagram. The glass expressed the non-exponential behaviour, and IH model was adopted to analyse the dipole-dipole interaction between Dy3+ and Dy3+ ions. 1DyGSBS glass has higher values of the stimulation of white light parameter, the stimulated emission cross-section (σPE), and the gain bandwidth (σPE×Δλeff) than the others. Furthermore, the gamma ray parameters, such as the mass attenuation coefficient (μ/ρ), the half and tenth value layers, the effective atomic number, the equivalent atomic number, the exposure and energy absorption buildup factors (EBF and EABF), and the fast neutron removal cross-section (ƩR) were analysed with Phy-X/PSD program. According to the outcomes of the present work, it is perceptible that these glasses, especially 1DyGSBS and 3DyGSBS, are great potential in white lighting and gamma ray shielding applications for the future.

Amorphous alloys with high Fe content for radiation shielding applications

In this research article, the radiation shielding properties of newly developed high Fe content amorphous alloys were reported. The chemical compositions of these alloys were Fe83B9C3Si4P1, Fe84B10C2Si2P, Fe85B8C3Si3P1, and Fe86B5C8P1. Monte Carlo simulation method was successfully used to study the problem of radiation propagation through theses alloys under suitable boundary conditions of vacuum. Our results indicate that MAC value decays as photon energy grows varying from 0.0997 to 0.0387, 0.0997–0.0387, 0.0998–0.0387, and 0.0998–0.0387 cm2/g for FBCSP1, FBCSP2, FBCSP3, and FBCSP4 respectively. However, gradual increase was observed in both parameters of mean free path (MFP) and half value layer (HVL) as energy increases. The maximum and minimum value of the effective atomic number (Zeff) was 23.09 and 22.97, 23.29 and 23.17, 23.41 and 23.30, and 23.4 and 23.29 for FBCSP1– FBCSP4 respectively. FNRC (Fast Neutron Removal Cross-section) values were: 0.1538, 0.1538, 0.1536, and 0.1561cm-1 for FBCSP1– FBCSP4 respectively. Moreover, an extensive comparison was reported between the radiation shielding proficiency of the studied alloys and that of the traditional materials. It can be concluded that, FBCSP alloys can conveniently replace the traditional materials in photon shielding application especially when space is a constraint.

The neutron cross section of barite-enriched concrete for radioprotection shielding in the range 1 meV–1 keV

We present a characterization of a series of barite-enriched concrete samples at the atomic scale using neutron-based techniques. In particular, neutron transmission measurements provide the macroscopic cross section (also known as neutron removal cross section) as a function of the incident neutron energy in the range 1 meV–1 keV. In this range, where fewer experimental investigations are available in the literature, the cross section is dominated by the scattering events from hydrogen, as opposed to the fast-neutron region (MeV-energy neutrons) where capture events by Ba are more important. Moreover, below 1 eV, the cross section depends on the molecular or crystal structure of the components. For each sample, the amounts of barium and hydrogen are provided by neutron resonance capture analysis and deep inelastic neutron scattering, respectively. We find that the amounts of barium and hydrogen are correlated, with a lower amount of hydrogen in the samples with more barium, likely because of the absence of some calcium-silicon-hydrate structures, whose formation is inhibited by the presence of barite. Moreover, we quantify the non-negligible contribution to the neutron macroscopic cross section arising from water molecules loosely bound in concrete. This contribution makes the shielding performance of concrete dependent upon the humidity and temperature conditions affecting the installation. Our results provide additional guidelines for radioprotection workers to determine the optimal concentration of barite in mixed gamma/neutron radiation environments.

Synthesis, structure, mechanical and radiation shielding features of 50SiO2–(48 + X) Na2B4O7–(2 − X) MnO2 glasses

A novel glass system with the composition 50SiO2–(48 + X) Na2B4O7–(2 − X) MnO2 (0 ≤ X ≤ 2 mol%) was synthesized using the classical melting method. The obtained FT-IR spectroscopy of the fabricated samples refers to the transformation of the structural unit BO3 into BO4. Ultrasonic velocities and elastic moduli were found to increase with the increase in the ratio of Na2B4O7 in the fabricated samples. MCNP-5 code was applied to determine the gamma-ray shielding characteristics. The results demonstrate that the glasses without MnO2 content have the best gamma-ray shielding capacity. The linear attenuation coefficient (LAC) varied in the range between 0.055 and 8.873 cm−1 for gamma photons between 0.015 and 15 meV. Moreover, the fast neutron removal cross section was calculated theoretically. The mass stopping power and the projected range were calculated using the Stopping and Range of Ions in Matter program (SRIM) for charged protons and alpha particles.

Gamma ray interaction studies of the PbCl2–SnCl2–P2O5 bioactive glass system for applications in nuclear medicine

Studies of bioactive glasses give an advanced roadbook to realize radiation applications in nuclear medicine and other medical applications. This paper aims to investigate the gamma ray interaction parameters of the PbCl2–SnCl2–P2O5 glass system. The mass attenuation coefficients (μm) of the selected bioactive glasses have been obtained using XCOM and dosimetry Phy-X/PSD programs in the photon energy range 10–150 keV and also correlated with those simulated through MCNP5 code. The other parameters, such as the effective atomic number (Zeff), electron density (Ne), and mean free path (MFP), tenth-value layer (TVL), and half-value layer (HVL) values have also been computed. Among all the selected bioactive glasses, the S4 bioactive glass has the lowest MFP, HVL, and TVL, showing that it is highly effective in absorbing gamma rays. The values of MFP of all samples (S1–S8) are also compared to the RS 253G18 and RS 360 commercial glasses at energy 150 keV. The fast neutron removal cross-sections have been obtained to study the fast neutron absorption behavior with the selected bioactive glasses.

A comparative study on the nuclear shielding properties of BiBr3 and PbSO4 incorporated composites

Detailed investigations on the photon and neutron attenuation properties of various BiBr3 and PbSO4 incorporated polyester composites have been carried out in terms of evaluating their potential use as new radiation shielding materials. Utilizing HPGe detector-based γ-ray spectrometry, the mass attenuation coefficient values of the polyester materials were calculated over a wide photon energy range of 59.5–1408 keV. The experimental results have been compared to those obtained using XCOM software and showed that the measured attenuation coefficient was in good agreement with the theoretical results at all photon energies studied. Moreover, BiBr3(20%) and PbSO4(20%) exhibit the minimum half value layers (5.94 and 6.58 cm at 661 keV) and highest radiation protection efficiencies (69.80 and 69.67% at 59.9 keV), while the neutron removal cross-sections of BiBr3(5%) and PbSO4(5%) samples were higher than the other composites studied.

Radiation attenuation and photoluminescence properties of host tellurite glasses doped with Er3+ ions

The application of shielding is one of the main protective measures in ionizing radiation safety. This paper addresses the influence of erbium oxide (Er2O3) amount fraction on shielding properties of the glass system with compound formula 75TeO2-10Nb2O5-10ZnO-5PbO (TNZP). Addition of Er2O3portions increased samples densities from 5.57 to 5.65 g/cm3. The attenuation properties for the different TNZP-Er2O3samples were simulated using Phy-X/PSD software at vary wide energy ranged from 0.015 to 15 MeV . Various radiation shielding parameters were evaluated including; linear (LAC) and mass (MAC) attenuation coefficients, the half (HVL)- and tenth (TVL)-value layers, the mean (MFP) free path, the total atomic (ACS) and electronic (ECS) cross-sections and fast (FNRCS) neutron-removal cross-section. These parameters were also verified by a comparison with the currently available shielding materials such as RS-253-G18, RS-360, RS-520 and, Chromite, Ferrite, Magnetite, and Barite. Morover the strong green and weak red emission estimated in the prepared glasses under excited 980 nm. Results show that TNZP with high Er2O3constituents is not merely an effective shield for photons but also a good candidate for neutrons protection and theraputic surgery for medical diagnostic applications. The provided esults showed lower FNRCS values compared to the Chromite, Ferrite, and Magnetite. Nevertheless, it can be noticed that the partially added density of Er2O3enhanced FNRCS.

Simulation studies on the radiological parameters of marble concrete

Radiation shielding is a popular subject in physics due to its wide utilization in different fields in parallel with technological development, and thus, recently many research studies have focused on this subject. Most works have been performed using simulation codes, as experimental studies are more difficult and require a technical set-up. Simulation works were performed in this study to obtain the radiation-shielding properties of marble concrete at gamma-ray energies of 0.511, 0.835 and 1.275 MeV. The simulations were done using the Phy-X/PSD code in order to obtain the linear attenuation coefficients (μ, cm−1). Some other radiological parameters, such as the mean free path, half-value length, tenth-value length, effective atomic number (Z eff), electron density (N eff), equivalent atomic number (Z eq), exposure buildup factor and fast neutron removal cross-section, were also obtained.

Development of SiO2 based doped with LiF, Cr2O3, CoO4 and B2O3 glasses for gamma and fast neutron shielding

Abstract In this study, the fast neutron and gamma-ray absorption capacities of the new glasses have been investigated, which are obtained by doping CoO,CdWO4,Bi2O3, Cr2O3, ZnO, LiF,B2O3 and PbO compounds to SiO2 based glasses. GEANT4 and FLUKA Monte Carlo simulation codes have been used in the planning of the samples. The glasses were produced using a well-known melt-quenching technique. The effective neutron removal cross-sections, mean free paths, half-value layer, and transmission numbers of the fabricated glasses have been calculated through both GEANT4 and FLUKA Monte Carlo simulation codes. Experimental neutron absorbed dose measurements have been carried out. It was found that GS4 glass has the best neutron protection capacity among the produced glasses. In addition to neutron shielding properties, the gamma-ray attenuation capacities, were calculated using newly developed Phy-X/PSD software. The gamma-ray shielding properties of GS1 and GS2 are found to be equivalent to Pb-based glass.

Systematic reduction of the proton-removal cross section in neutron-rich medium-mass nuclei

Single-neutron and single-proton removal cross sections have been measured for medium-mass neutron-rich nuclei around Z=50 and energies around 1000A MeV using the FRagment Separator (FRS) at GSI. The measured cross sections confirm the relative low values of the proton-removal cross sections, observed since a long time ago and not yet understood. Model calculations considering the knock-out process together with initial- and final-state interactions describe the measured neutron-removal cross sections. Proton-removal cross sections are, however, significantly over-predicted by the same calculations. The observed difference can be explained to a large extent by the knock-out of short-range correlated nucleons from dominant neutron-proton pairs in neutron-rich nuclei.

Gamma-ray/neutron shielding capacity and elastic moduli of MnO–K2O–B2O3 glasses co-doped with Er3+ ions

Gamma-ray/neutron shielding capacity and mechanical properties of erbium-doped potassium manganese borate glasses with the chemical form of (1 − x)MnO–29K2O–70B2O3–xEr2O3: x = 0–1 mol% coded as E0–E5 via bond compression model, XCOM software, and PHITS simulations have been investigated. The bulk modulus (KB.C) values increased from 90.19 for E0 glass sample with free Er2O3 to 101.24 GPa for E5 glass sample with Er2O3 = 1 mol%. The Young’s modulus (EB.C) increased from 102.68 GPa to 115.38 GPa, while the longitudinal modulus (LB.C) increased from 142.31 GPa to 159.81 GPa for E0–E5 glasses. Poisson’s ratio (σB.C) decreased from 0.310261 to 0.310065 with the increase of Er3+ ions in the investigated glasses. Hardness of E0–E5 glasses was increased from 4.96 GPa to 5.58 GPa. The mass attenuation coefficient (µ/ρ) values were the highest at the least energy of 0.284 MeV with values of 0.1080, 0.1096, 0.1113, 0.1129, 0.1145, and 0.1161 cm2 g−1 for E0, E1, E2, E3, E4, and E5, respectively. Moreover, radiation protection efficiency (RPE) of the E0–E5 glasses was estimated using PHITS simulation code. The highest RPE was observed for E5 glass with a thickness of 5 cm. Finally, the neutron shielding capacity of E0–E5 glasses was evaluated in terms of the fast neutron removal cross section (FNRCS). The values of FNRCS increased by adding Er2O3 content and a sharp increase was observed at xEr2O3: x = 0.8 mol%. Generally, one can conclude that the E5 glass sample with the highest Er2O3 (1 mol%) concentration is the best sample as radiation shield among all the studied glasses.

Gamma-ray attenuation, fast neutron removal cross-section and build up factor of Cu2MnGe[S, Se, Te]4 semiconductor compounds: Novel approach

This study is original work on semiconductor materials for gamma-ray detectors and fast neutron removal cross-section. This work is focused on the investigating of γ-ray interactions using Cu2MnGeS4, Cu2MnGeSe4, and Cu2MnGeTe4 semiconductor compounds. The photon interaction parameters (MAC, LAC, HVL, TVL, MEF, ACS, ECS, Zeff, Neff, Ceff, Zeq, EBF, and EABF) of the three different semiconductor compounds were graphically presented within 0.015–15 MeV energy range. A useful comparison with regular radiation shielding with standard glass materials with these samples has been developed. Cu2MnGeSe4 and Cu2MnGeTe4 semiconductor compounds have higher values of MAC and LAC compared with ordinary and steel magnetite concrete at the 0.1, 10, and 15 MeV. Interestingly, the checked semiconductor samples named Cu2MnGeSe4 andCu2MnGeTe4 have lower values for HVL and MFP than some commercial glasses used in radiation safety applications. At 15 KeV, Zeff values are 27.13, 32.11 and 39.21 and Neff values are 3.41, 2.71 and 2.47 × 1023 electron cm−3 for Cu2MnGeS4, Cu2MnGeSe4, and Cu2MnGeTe4 semiconductor compounds, respectively. Semiconductor compounds have better neutron protection features compared to RS-520, RS-253-G18, and RS-360 standard glassy materials. In a large energy range, the third sample, Cu2MnGeTe4, showed high sensing for gamma-rays and neutrons. These studies are very important for the manufacture of detectors for semiconductors used for X and gamma-ray measurements (detection of radiation).

Structural and nuclear shielding qualities of B2O3–PbO–Li2O glass system with different Ag2O substitution ratios

Structural and gamma-ray/neutron radiation protection characteristics of (50-x)B2O3 +40PbO+10Li2O + xAg2O (x = 0, 2.5, 5, 7.5, 10 wt fraction (wt) %) glass system encoded BPLA glasses have been extensively surveyed. The structure of the prepared glasses has been investigated over X-Ray Diffraction (XRD) patterns. With the addition of Ag2O, the glasses' amorphous structures have not deteriorated, and the density and molar volumes of BPLA glasses inversely varied. Mass attenuation coefficients (MAC) for BPLA glasses have been generated enjoying Monte Carlo N-Particle- Extended (MCNPX) simulation code for the broad gamma-ray energy range of 0.015–15 MeV. It has been observed that the MAC values of the BPLA10 glass are higher than the others at all energy levels. Furthermore, while Ag2O concentration in the glass has increased, Half Value Layer (HVLs) Energy Absorption and Exposure Buildup Factors (EABFs, and EBFs) have dropped off for photon energies which are important for shielding applications. It has been noticed from these results that owning higher equivalent atomic number (Zeq) values, BPLA10 can be employed effectively for gamma-ray attenuation. Lastly, the results found for fast neutron removal cross-sections (∑R) have shown that the Ag2O additive grew the density and ∑R values of the glasses. As with photon shielding, it is observed that BPLA10 glass can be more preferable in terms of neutron retention according to other glasses. One can conclude that Ag2O enhances the shielding capacity of the glass system studied and BPLA10 glass can be considered as a good material for gamma-rays/fast neutrons shielding.