Fast Neutron Removal Cross Sections Research Articles

Flexible stretchable low-energy X-ray (30–80 keV) radiation shielding material: Low-melting-point Ga1In1Sn7Bi1 alloy/thermoplastic polyurethane composite

A highly flexible stretchable thermoplastic polyurethane (TPU) composite loaded with a low-melting-point Ga1In1Sn7Bi1 multiprincipal element alloy (LMPEA) was prepared, and its radiation shielding performance was evaluated. The fluid characteristic of LMPEA and the flexibility of TPU enable good interface compatibility. Ga1In1Sn7Bi1 LMPEA consists of two eutectic structures, and the liquid gallium-rich phases are distributed at the boundary of the InBi intermetallic compound and Sn solid solution. In the low-photon energy range of 30–80 keV, LMPEA has a theoretical specific lead equivalent of 0.803 mmPb/mm and a theoretical weight reduction of 17.27% compared with lead. To evaluate the photon attenuation capability for the LMPEA/TPU composites, the Phy-X procedure and Monte Carlo simulations were used to determine the shielding parameters, such as the mass attenuation coefficient, linear attenuation coefficient, half-value layer, tenth-value layer, mean free path, effective atomic number, and fast neutron removal cross section. The attenuation performance test of X-ray protective materials measured the actual lead equivalent. At the same thickness, the LMPEA/TPU composite (66.667, 50.000 wt% LMPEA loading) has a higher measured lead equivalent than the in-service medical shielding materials, which meets the lead equivalent requirements of X-ray protective clothing. LMPEA/TPU composites are nontoxic, lightweight, and have excellent low-energy X-ray shielding ability, offering great potential for application in medical wearable materials.

Physical, structural, thermal, and mechanical features combined with neutron and gamma radiation attenuation qualities of Sm2O3 doped transparent borate-rich glasses

Current work presents the synthesis of B2O3–Gd2O3–Li2O–Na2O–LiF‒Sm2O3 glass system via melt-quench approach and scrutiny of its mechanical, thermal, structural, physical, and nuclear radiation attenuation aspects. Raman scattering and Fourier transform infrared spectra revealed B–O stretching modes of BO4 groups linked to BO3 units with nonbridging oxygen atoms and BO3 and BO4 units' existence in the glass structure. By differential scanning calorimetry, glass transition and crystallization temperatures are identified. Relevant analysis showed all glasses' good thermal stability where glass transition temperature varied at 372–407 °C range. ΣR (fast neutron removal cross-section) and for energy 0.025 eV neutrons σT (total cross-section) are computed. In all glasses, 49.25 B2O3–10Gd2O3–10Li2O–10Na2O–20LiF-0.75Sm2O3 (mol%) sample holds higher ΣR (= 0.10207 cm−1). 48B2O3–10Gd2O3–10Li2O–10Na2O–20LiF–2Sm2O3 (mol%) glass possesses greater σT (= 736.675 cm−1) for thermal neutrons, hinting at added Sm2O3's favorable influence as Sm owns a better ability for neutron absorption than B. By Phy-X/PSD, μ/ρ (mass attenuation coefficient) is obtained at photon energy extent 15 keV‒15 MeV. Sm2O3 inclusion from 0 to 2 mol% minorly enhanced the μ/ρ values. Buildup factors estimated via geometric progression fitting method at 1–40 mean free path and energy 0.015–15 MeV span are maximal at medium energy region owing to Compton scattering process. 48B2O3–10Gd2O3–10Li2O–10Na2O–20LiF–2Sm2O3 (mol%) sample shows superior γ-ray blocking capacity in all glasses, suggesting Sm2O3's positive effect. Elastic moduli and Poisson's ratio are computed theoretically by bond compression and Makishima–Mackenzie models. It is identified that all glasses could tolerate longitudinal stress over shear stress.

Lead-free inorganic metal perovskites beyond photovoltaics: Photon, charged particles and neutron shielding applications

Over the last few years, lead-free inorganic metal perovskites have gained impressive ground in empowering satellites in space exploration owing to their material stability and performance evolution under extreme space environments. The present work has examined the versatility of eight such perovskites as space radiation shielding materials by computing their photon, charged particles and neutron interaction parameters. Photon interaction parameters were calculated for a wide energy range using PAGEX software. The ranges of heavy charged particles (H, He, C, N, O, Ne, Mg, Si and Fe ions) in these perovskites were estimated using SRIM software in the energy range 1 keV–10 GeV, and that of electrons was computed using ESTAR NIST software in the energy range 0.01 MeV–1 GeV. Further, the macroscopic fast neutron removal cross-sections were also calculated to estimate the neutron shielding efficiencies. The examined shielding parameters of the perovskites varied depending on the radiation type and energy. Among the selected perovskites, Cs2TiI6 and Ba2AgIO6 displayed superior photon attenuation properties. A 3.5 cm thick Ba2AgIO6-based shield could reduce the incident radiation intensity to half its initial value, a thickness even lesser than that of Pb-glass. Besides, CsSnBr3 and La0.8Ca0.2Ni0.5Ti0.5O3 displayed the highest and lowest range values, respectively, for all heavy charged particles. Ba2AgIO6 showed electron stopping power (on par with Kovar) better than that of other examined materials. Interestingly, La0.8Ca0.2Ni0.5Ti0.5O3 demonstrated neutron removal cross-section values greater than that of standard neutron shielding materials - aluminium and polyethylene. On the whole, the present study not only demonstrates the employment prospects of eco-friendly perovskites for shielding space radiations but also suggests future prospects for research in this direction.

Attenuation features of Ag2ZnSnS4, Ag2ZnSnSe4, ZnS, and Ag2S compounds against indirect ionizing radiation using Phy-X/PSD software

Four sulfide compounds' attenuation features of gamma-ray (Ag2ZnSnS4, Ag2ZnSnSe4, ZnS, and Ag2S) were described in this paper by a new software Phy-X/PSD. We calculated radiation attenuation parameters for the selected samples for a broad range of energies (0.015–15 MeV), including linear attenuation, the mean free path, the half-value layer, and total atomic and electronic cross-sections. The effective atomic number and the effective conductivity were also analyzed to investigate the radiation attenuation features. Also, the analyzed samples' buildup factors were studied. The samples’ parameters were compared to materials frequently used to shield against radiation, including ferrite, chromite, barite, magnetite, and RS (253 G18, 360, 520) glass. Due to MFP and HVL values, Ag2S has better attenuation features than all the other samples utilized in the comparison. Fast neutron removal cross-sections (FNRCS) were also studied, and the best neutron attenuation composite among the samples under study, according to the FNRCS data, is Ag2S (0.116 cm−1).

Comprehensive study on structure, shielding properties of Ga-In-Sn-Bi-Zn alloys: potential use for low energy radiation

Low-melting point Ga-In-Sn-Bi-Zn alloys were prepared using a vacuum melting technique as a novel radiation shielding material. To evaluate the interaction between alloys and photons in the energy range of 1–10000 keV, the WinXCom and Phy-X procedures are used to determine the shielding parameters for the Ga-In-Sn-Bi-Zn alloys, such as the mass attenuation coefficient, linear attenuation coefficient, half-value layer, tenth-value layer, mean free path, effective atomic number. Simultaneously, the energy absorption and exposure buildup factors, fast neutron removal cross section values is also calculated and the comparative lead equivalent (M) and weight reduction over lead for the alloy samples are compared. It is observed that the Ga2In2Sn2Bi3Zn1 alloy have exhibit superior comprehensive radiation attenuation, with a weight reduction of 2.948% compared to lead for the same shielding performance in the 30–90 keV range. After being irradiated by 40 keV He + irradiation system for 120 h, the phase structure of Ga2In2Sn2Bi3Zn1 alloy remained unchanged and that it shows excellent radiation tolerance. Combined with field emission scanning electron microscopy, x-ray diffraction, differential scanning calorimetry and thermogravimetric analysis results indicate that Ga2In2Sn2Bi3Zn1 is a eutectic alloy with a five-phase complex-regular structure and a melting point of 66.95 °C. The alloy exhibits excellent fluid compliance in the molten state when blended with polymers to prepare composites. The alloy filler is uniformly and continuously distributed in the polymer matrix, which ensures the reliability of the radiation shielding properties of the composites.

INVESTIGATION OF NUCLEAR RADIATION INTERACTION PARAMETERS OF NICKEL- BASED SHAPE MEMORY ALLOYS

In this study, the fast neutron removal cross section (FNRCS), mass attenuation coefficient (μ/ρ), half-value thickness (HVL), tenth value thickness (TVL), mean free path (λ), total electronic cross section (σte), totalmolecular cross section (σtm), effective atomic number (Zeff) and the effective electronic density (Neff) the valueswere calculated for nickel-based shape memory alloy at different energy. Important another nuclear attenuationparameter relevant to shielding i.e. the fast neutron removal cross section (FNRCS) was be calculated for alloys.NiTiPt possesses the best FNRCS (= 0.143) among the present studied alloys.

Radiation shielding parameters and Micro-Raman spectral analysis of some pyroclastic rocks

In this study, the radiation shielding parameters of some pyroclastic rocks (Karabakir, Elazığ) were experimentally measured at 59.54–661.62 keV energy region. In addition, theoretical mass attenuation coefficients were calculated. Fast neutron removal cross section, exposure buildup factor, mass stopping power and projected range values for proton (H1) and alpha (He+2) particles were theoretically determined. The equivalent dose rates due to fast neutrons absorption by rock samples was measured experimentally using a241Am–Be fast neutron source with 10 mCi activity. Also, the elemental analysis of pyroclastic rocks was done by instrumental neutron activation analysis and inductively coupled plasma mass spectrometry. Minerals type and rock strength were evaluated by micro-Raman spectroscopy methods. The dose rate at detector is D0 when there is no sample between the neutron source and the detector, the dose rate at detector is Dd when there is a K-8 rock sample. The difference between the dose rates (Ds), was calculated and the equivalent dose rate absorbed by the K-8 rock sample was obtained as 0.2667 μSv⁄h. It is observed that K-8 rocks sample is a promising choice for gamma, neutron, proton and alpha shielding.

Investigation of gamma ray, electron, and neutron interaction parameters of some topological insulating materials

The gamma ray, neutron, and electron radiation interaction parameters were calculated for some topological insulating (TI) materials such as Sb2Te3, Bi2Se3, Bi2Te2Se and Bi2Te3 at various energies. The gamma ray interaction parameters such as mass attenuation coefficient, half value layer, tenth value layer, effective atomic number, equivalent atomic number, exposure buildup factor, and energy absorption buildup factor were calculated in the energy range of 0.015–15 MeV at penetration depths of 1–40 mfp by using the five-parameter Geometric Progression (G-P) fitting approximation method. The buildup factors were found to be dependent on the energy of the incident photon, penetration depth, and material elemental composition, and they were also found to be higher for Sb2Te3 than for other TI materials throughout the energy region of investigation. The neutron interaction parameters, such as fast neutron removal cross section, were calculated for the selected topological insulator materials using Phy-X/PSD software and found to be higher for Bi2Te3 than for the other three materials. The electron stopping power values were calculated for the selected topological insulator materials in the energy range of 0.01 MeV to 1000 MeV using the ESTAR program. It was found that the stopping power values decreased slowly with increasing electron energy in the lower energy region, remained almost constant in the medium energy region, and increased rapidly in the higher energy region.

Theoretical Investigation of Fast Neutron and Gamma Radiation Properties of Polycarbonate-Bismuth Oxide Composites Using Geant4.

The gamma mass (µm) and linear (µ) attenuation coefficients of polycarbonate-bismuth oxide composites (PC-Bi2O3) with different bismuth oxide weight factors were investigated theoretically using EpiXS and a Monte Carlo simulation-based toolkit and Geant4 within an energy range between 0.1 and 2 MeV. The wide energy ranges of gamma rays and neutrons were chosen to cover as many applications as possible. The attenuation coefficients were then used to compute the half-value layers. The effective atomic numbers and effective electron densities of the studied samples obtained by EpiXS were compared as well. In order to further evaluate the shielding effectiveness of the studied samples, the thicknesses of all the investigated samples equivalent to 0.5 mm lead at a gamma energy of 511 keV were compared using a Geant4 code simulating a female numerical phantom with a gamma source placed facing the chest and a cylinder-shaped shield wrapped around the trunk area. The fast neutron removal cross sections of the investigated samples were studied to evaluate the effect of the weight factor of nanocomposites on the neutron shielding capabilities of the polymer as well.

On the neutron shielding efficacy of flexible silicone infused with CdO nanoparticles

Shielding material is used for protection against harmful effect of ionizing radiations. This paper is aimed at studying the prospects of silicone elastomer based nanocomposites as neutron shielding material. Cadmium oxide (CdO) nanoparticles and multi-walled carbon nanotubes (MWCNTs) were used as filler medium in the nanocomposites, due to their exceptional neutron attenuation properties. The CdO nanoparticles were synthesized using composite-hydroxide-mediated (CHM) method and their structural purity was confirmed with x-ray diffraction data. Silicone/CdO/MWCNTs nanocomposites were fabricated by room-temperature-vulcanization (RTV) method, with different concentrations of nano-fillers (3, 6 and 9 % wt of CdO; 1 % wt of MWCNTs). The half value layer (HVL) thickness of the nanocomposites were found to be 7.44 cm, 5.90 cm and 5.72 cm, while the neutron removal cross sections were noted as 0.09307, 0.11732, and 0.12107 for the nanocomposites containing 3%, 6% and 9% of CdO, respectively. The Phy-X software was used to calculate the fast neutron removal cross-section and found it consistent with the experimental results. The results revealed that adding nano-fillers (CdO nanoparticles and MWCNTs) into silicone matrix not only enhanced the neutron shielding efficacy of nanocomposites but also have improved their mechanical properties and making it useful for neutron shielding applications.

A comprehensive study on optical features, gamma photon buildup factors and neutron shielding capability of B2O3-SB2O3-LI2O-BI2O3 glasses

ABSTRACT. Linear, nonlinear optical properties, photon buildup factors, and neutron shielding capability of glasses with chemical composition (65-x)B2O3-10Sb2O3-25Li2O-xBi2O3, where x = 0 (BSLB0) – 20 (BSLB20) mol% with steps of 4 mol% were examined. Molar refractivity (Rmolar) and molar polarizability (αmolar) were increased as Bi2O3 content mol% increase in the examined BSLB-glasses. The values of metallization criterion (Mcriterion) confirmed that the BSLB-glasses were non-metallic materials. The static (εstatic) and optical (εoptical) dielectric constants having the same trend of the refractive index (noptical). Values of optical electronegativity (χ*) were reduced from 0.825 for BSLB0 (Bi2O3 = 0 mol%) glasses to 0.758 for BSLB20 (Bi2O3 = 20 mol%) glasses. The linear electric/dielectric susceptibility (χ(1)) increased from 0.370 to 0.397. The nonlinear optical susceptibility (χ3) and nonlinear refractive index n2optical were enhanced by increasing Bi2O3 content in the BSLB-glasses. The BSLB20 glasses presented the least exposure and energy absorption build-up factors (EBF and EABF) at all considered thickness. BSLB20 sample achieved the best fast neutron removal cross section ( ) shield among all glasses. The total stopping powers (TSP) follows the trend (TSP)BSLB0 < (TSP)BSLB4 < (TSP)BSLB8 < (TSP)BSLB12 < (TSP)BSLB16 < (TSP)BSLB20. The electron absorbing and hence shielding capacity of the BSLB-glasses improves as their Bi2O3 content increase. 
 
 KEY WORDS: Antimony lithium-borate glasses, Optical properties, Buildup factors, Neutron shielding
 
 Bull. Chem. Soc. Ethiop. 2022, 36(4), 949-962. 
 DOI: https://dx.doi.org/10.4314/bcse.v36i4.19

TeO2 for enhancing structural, mechanical, optical, gamma and neutron radiation shielding performance of bismuth borosilicate glasses

The synthesized 12Bi2O3– 8BaO–12ZnO-0.5CeO2-17.5SiO2- (50-x) B2O3- xTeO2 glasses with x = 0, 10, 20, 30 and 40 mol% (coded BiTe-0 to BiTe-40) were investigated in terms of physical, structural, optical and mechanical properties to examine the influence of CeO2 and TeO2 on the heavy metal oxide (HMO) borosilicate network. Density values increased continuously with increasing TeO2 concentration with BiTe-40 glass exhibiting maximum value of 5.0875 gcm−3. This property helped in enhancement of refractive index values from 1.769 for BiTe-0 to 1.942 for BiTe-40. Fourier transform infrared (FTIR) analysis of studied glasses revealed the presence of additional small peak at 683 cm−1 in BiTe-30 and BiTe-40 which confirmed the formation of stable TeO4 units in the glass network. The deep brown colour of the glass existing due to bismuth's presence was nullified by CeO2 and TeO2 additives which improved transparency of the glass. Urbach analysis of these glasses led to optical bandgap variation between 3.27 eV and 2.73 eV for 0–40 mol% TeO2 concentration. Makishima and Mackenzie model was utilized for evaluation of elastic property of the glasses, and Poisson's ratio ranging between 1.935 and 1.953 was obtained. Vickers micro-indentation test on the current glasses revealed decreasing microhardness from 4.116 to 4.076 GPa with TeO2 variation from 0 to 40 mol% at 9.8 N load. Gamma radiation shielding parameters were determined using Phy-X/PSD software and it was found that BiTe-40 glass produce maximum MAC (mass attenuation co-efficient) values in high photon energy region 3.5–15 MeV. The present article also contains a detailed emphasis on behaviour of gamma radiation build-up factors at different incident photon energy and TeO2 concentration. The increasing trend of exposure build up factor (EBF) was seen with increasing penetration depth inside the samples at all energies, indicating that glasses of larger thickness improve the escape probability of photons. Meanwhile, fast neutron removal cross-section (FNRCS) was highest for BiTe-10 sample (0.10118 cm−1) which also surpassed the value of ordinary concrete (0.093 cm−1). Overall, the present glass system bested other conventional shields available commercially in terms of gamma and neutron radiation shielding effectiveness.

Fabrication, physical, mechanical, and radiation protection properties of bismo-borate glasses containing La3+ + Eu3+ as additive ions

This research work has focused on the physical, elastic-mechanical, and shielding features of bismuth-borate glass samples consisting of varied amounts of La2O3 and Eu2O3 as additive agents to improve these characteristics. The effect of density and [La3++ Eu3+] ions mol % have been projected on the evaluated elastic moduli including Poisson's ratio and protection effectiveness against incoming γ-ray and neutron. Makishima-Mackenzie multi-components theory was employed to calculate the mechanical parameters. We found that the Vickers's microhardness and the Passion's ratio depend on both sample's density and [La3++ Eu3+] ions mol%, but follows the trend of oxygen molar volume (OMV). The mass attenuation coefficient (MAC) has been calculated in the energy range 0.015 < E < 15 MeV via XCOM, Phy-X/PSD program, and compared with Monte Carlo simulations at selected photon energies. Accordingly, other important radiation shielding parameters such as linear attenuation coefficient (LAC), transmission coefficient (TF), and radiation protection effectiveness (RPE) were calculated for the current glass systems. Also, the exposure and energy adsorption buildup factors (i.e., EBF and EABF) of the fabricated glasses were obtained. Moreover, the fast neutron removal cross section (ΣR) were evaluated and found to have the highest value of 0.11884 for the sample of [La3++ Eu3+] = 0.5. Correlation between the elastic moduli and the gamma-ray shielding features was established and explained in terms of density, molar fraction, oxygen molar volume, and oxygen packing density.

Optical transmission, polarizability, and photon/neutron shielding properties of Bi2O3/MnO/B2O3 glass system

The Bi2O3/MnO/B2O3 glass system was successfully investigated for their optical and radiation protection features. The optical characterization of the glasses was achieved by estimating and analysing important optical parameters such as molar volume, refractive index, and molar refractivity using standard equations. The photon mass attenuation coefficient MAC of the glasses was estimated by FLUKA Monte Carlo simulation and validated by XCOM computation for energies 0.015 – 15 MeV. Further, the fast neutron removal cross section of the glasses was estimated theoretically. The optical and radiation shielding parameters showed strong dependence on the chemical composition. The molar volume of the BMB-Ax glasses decreased from 40.658 to 36.895 cm3/mole as the molar concentration of B2O3 increased relative to Bi2O3 and MnO. In addition, the refractive index of BMB-Ax reduced from 2.60 to 2.34 while the molar refractivity reduced from 26.73 to 22.05 × 10−24 cm3 for BMB-A1 –A3 accordingly. The MAC ranged from 89.629 to 0.039, 76.162–0.037, and 67.414–0.036 cm2g−1 for BMB-A1, and BMB-A2, and BMB-A3. The effective atomic number of the glasses was within the range: 24.62 – 78.05, 18.27 – 76.60, and 15.41 – 75.49 while the fast neutron removal cross section was estimated to be equal to 0.1002, 0.0972, and 0.0967 cm−1 for B2O3 molar concentration of 3, 4, and 6 respectively. The BMB-Ax glasses showed good optical and radiation shielding properties that makes them potentially useful in optical and radiation protection applications such as photonics and shielding respectively.

Synthesis and characterization of the optical MgO-BaO-B2O3-TeO2-MnO2 glass system

The paper reports on the preparation and characterization of the optical 15MgO-15BaO-(59.5-x)B2O3-(10+x)TeO2 glass system, with (x = 0 (MBBMn-1), 10 (MBBMn-2), 20 (MBBMn-3), and 30 mol% (MBBMn-4)). Using the melt-quench experimental synthesis method, we prepared our glass system and the influence of TeO2 on the physical, structural, optical, and radiation shielding properties were studied. The bandgap (Eopt), Urbach energy (∆E), refractive index (n), and other parameters were calculated using UV data. The stopping power and range of electron, proton, α-particle and carbon ion were estimated for kinetic energies 0.015–15 MeV. Also, the fat and thermal neutron cross sections were estimated following the standard procedures. The structural evaluation of the glass network as well as the functional groups inherent in the structure was explored using FTIR and Raman spectra. At particle energy of 15 MeV, the range of electron was estimated as 25.89, 22.47, 20.49, and 19.79 mm in MBBMn-1–MBBMn-4 respectively. Also, for proton, α-particle, and carbon ion the projected range was 1080, 100.02 and 10.67 µm in MBBMN-1; 1030, 96.86, and 10.44 µm in MBBMN-2; 986, 93.95, 10.26 µm in MBBMN-3; and 942, 91.03, and 10 µm in MBBMN-4. The fast neutron removal cross section was 0.1069, 0.1066, 0.1063, and 0.1044 cm-1 for MBBMn-1 – MBBMn-4 in that order while the total cross section of thermal neutrons declined from 95.7025 to 74.8538 as the molar concentration of TeO2 increased from 10 to 40 mol% in the MBBMn glasses.

The properties of silicate glass specimens for photon, neutron, and charged particles shielding: The roles of Bi2O3

This experimental research aimed to study the photons, neutrons, and charged particles shielding properties of the glass specimens in the ratios xBi2O3: 5Li2O: 20ZnO: (75-x)SiO2 where; x = 20, 25, 30, and 35 mol%. The specimens have been synthesized by the melt-quenching technique at 1200 °C. The WinXCom program used to compute the theoretical values of the mass attenuation coefficient (MAC). The Compton scattering technique is employed to be in the experiment for comparing the theoretical values in the energy range 0.225 MeV–0.662 MeV from the Cs-137 source. The result found that density and molar volume similarly increase and created non-bridging oxygen (NBO) in glass structure. The MAC, effective atomic number (Zeff), and effective electron density (Neff) similarly abated with energy aggrandized and depended on the Bi2O3 concentrations. The half-value layer (HVL) and tenth-value layer (TVL) showed less thickness than other materials in the radiation shielding ability. The energy absorption buildup factor (EABF) and exposure buildup factor (EBF) are the same trends and depend on the penetration depth and energy range. The total mass stopping power (TMSP) and projected range (PR) have been reported using the SRIM program for charged particles shielding properties, and also concluded to calculate the fast neutron removal cross-section (FNRCS).

Synthesis and characterization of B2O3–Bi2O3–SrO–Al2O3–PbO–Dy2O3 glass system: The role of Bi2O3/ Dy2O3 on the optical, structural, and radiation absorption parameters

In the present study, a number of glass samples with the chemical signature: 70B2O3+(10-x)Bi2O3+5SrO+10Al2O3+5PbO+xDy2O3 were prepared and investigated for their structural, physical, optical, and radiation (gamma rays and fast neutron absorption) properties. The optical absorption data was used to measure the optical bandgap and Judd-Ofelt parameters. Based on photoluminescence decay spectral features stimulated emission cross-section and quantum efficiency were measured. The mass attenuation coefficient and the effective atomic number of the glass samples were observed to increase with the addition of Dy2O3. The addition of Dy2O3 also played a positive role in the charged particles absorption capacity of the glasses. In addition, the fast neutron removal cross-section of the glass samples increased from 0.0669 to 0.0713 cm−1 as molar concentration of Dy2O3 was increased from 0.1 to2.5 mol%. The synthesized glasses showed key characteristics that made them attractive for optical as well as radiation protection applications.

Monte Carlo simulations and phy-X/PSD study of radiation shielding and elastic effects of molybdenum and tungsten in phosphate glasses

The mechanical and shielding characteristics of (100 − x)% NaPO3−x% MoO3 (where x = 20,40,60) and (100-x)% NaPO3-x% WO3 (where x = 20,40,60) glass systems were studied to evaluate their ability to act as shielding materials. Using the Makishima-Mackenzie theory, the mechanical parameters of all glass samples and their dependence on the MoO3 content (mol%) for the first series and on the WO3 content (mol%) forthe second glass series were also investigated. The results showed thatthe mechanical properties and micro hardness were significantly enhanced by increasing the concentration of MoO3 from 20 to 60% for the first glass series and the concentration of WO3 from 20 to 60% for the second glass series. The shielding parameters of both glass series were also studied. The mass attenuation coefficient (μm) was computed by the Phy-X/PSD program for energies ranging from 0.015 to 15 MeV. The results are in excellent agreementwith the results calculated by the WinXCom software program and the results simulated by Geant4 Monte Carlo simulation. The computed μm values were used to deduce the other significant shielding parameters for all glass samples. The fast neutron removal cross-sections of all glass samples were examined and compared with those of standard materials. A strong correlation between the shielding parameters and the molar volume, oxygen packing density, and oxygen molar volume was found. The results revealed that thestudied glasses possessed superior shielding properties, especially the glass sample 0.4NaPO3-0.6MoO3 (mol%) which showed the most promising characteristics for radiation-shielding applications among the tested glasses.

High impact tungsten-doped borosilicate glass composite for gamma and neutron transparent radiation shielding

The preparation of transparent glass composites with enhanced shielding parameters is aimed at by all researchers in the radiation shielding field. In the current study, a novel tungsten-doped borosilicate glass composite with 1–5 mol % was prepared by means of melt quenching method at 1100 °C. Using both X-ray diffraction (XRD) and Fourier Transform Infrared Spectroscopy (FTIR), the amorphous nature and the influence of W+3 ions were examined, respectively. Gamma shielding parameters, such as the coefficients of mass attenuation, the Exposure Build-up Factors (EBF) up to 40 mfp penetration depth, the effective atomic number (Zeff), and the equivalent atomic number (Zeq) at the energy range 0.015–15 MeV were investigated. Additionally, the fast neutron removal cross-sections had been determined. The obtained results indicated that with low tungsten concentrations: 1–5 mol %, the prepared glass composite has gamma attenuation capability equivalent to those previously obtained with higher concentrations of lead or bismuth and barium doping and lower EBF. These results nominated the prepared glass composite for use in gamma and neutron shielding applications, especially those requiring transparent shielding, like radiation therapy monitoring rooms.

Calculation of Gamma and Neutron Shielding Parameters for Reinforced Polymer Composites

Abstract In this study, the shielding parameters for isophorone diamine (IPDA) with different ratios of barite (BaSO4), boron carbide (B4C), and aluminum oxide (Al2O3) composites were theoretically investigated. The mass attenuation coefficients (μm) were calculated at the photon energy range (1 keV to 20 MeV) using the xcom program. The obtained data were used to calculate the linear attenuation coefficients (μ), relaxation lengths (λ), half value layer (HVL), and tenth value layer (TVL) for the same range of energy. For comparison, five other shielding materials, ordinary concrete, high-density polyethylene, borated polyethylene, lithium polyethylene, and water, were also studied. The macroscopic fast neutron removal cross-sections (∑R) were calculated for the selected composites. The obtained results show that the shielding parameters strongly depend on the photon energy, chemical composition, and density of the investigated materials. The dependence of mass attenuation coefficients and macroscopic fast neutron removal cross section on the chemical composition of the selected polymer composites was discussed. Barite composite is seen to be a good attenuating material; aluminum oxide composite is a reasonable attenuating behavior, while Boron composite shows a relatively weak attenuating properties. The results obtained through this work can be used to understand the behavior and shielding effectiveness of the selected polymer composites.