Conventional Shielding Materials Research Articles

Yttria-doped geopolymers: Environmentally friendly and effective materials for shielding concrete in gamma radiation facilities

The use of geopolymer in place of ordinary Portland cement for concrete design and constructure is gaining attraction due to environmental and health considerations. Geopolymers must have high gamma radiation shielding competence in order for them to be useful for radiation shielding concrete. In an attempt to improve the gamma absorption capacity of a metakaolin-based geopolymer matrix, 10 % (GEO-10Y), and 20 % (G-20Y) yttria (Y2O3) was mixed with GEO through a solid-state reaction process. In this study, the influence of adding yttria on the physical and gamma shielding parameters of GEO was investigated. The densities of GEO, GEO-10Y and GEO-20Y were obtained as 2.28, 2.52 and 2.37 g/cm3, respectively. Through simulation using FLUKA code, the mass attenuation coefficients (MAC) and other relevant shielding quantities were estimated. The MACs of GEO, GEO-10Y, and GEO-20Y were within the range of 0.0213–6.6429 cm2/g, 0.0282–13.3923 cm2/g, and 0.0291–14.5136 cm2/g, respectively. The addition of yttria improved the gamma photon shielding competence of the metakaolin-based geopolymer by increasing the MAC and reducing photon buildup factors within 15 keV–15 MeV photon energy range. The shielding effectiveness of the yttria-doped GEO compares well with conventional shielding materials. Yttria-doped geopolymer can be used to produce effective and environmentally-friendly gamma shielding concrete.

Ultratough and self‐healable electromagnetic interference shielding materials with sandwiched silver nanowires in polyurethane composite films

AbstractThis study presents a facile self‐healing electromagnetic interference (EMI) shielding composite by sandwiching a layer of silver nanowires (AgNWs) between two layers of self‐healing polyurethane (SPU). The AgNWs layer forms an interconnected conductive network that effectively reflects and absorbs electromagnetic radiation, providing efficient EMI shielding. The SPU layers contribute autonomous healing of mechanical damages and restoring structural integrity and conductive pathways. The composite films exhibit remarkable EMI shielding effectiveness (SE) (up to 64.6 dB), exceptional mechanical toughness (106.4 MJ/m3), and self‐healing capabilities, outperforming conventional shielding materials. The synergy between AgNWs and SPU layers offers lightweight, flexible, tough, and self‐healing properties, making this material highly promising for applications in wearable electronics, aerospace, and automotive industries where durability and long‐term reliability are critical.Highlights Facile fabrication of sandwiched AgNWs layer between SPU films. Sandwiched AgNWs/SPU films with exceptional EMI shielding. AgNWs form conductive networks for efficient EMI shielding. Remarkable mechanical toughness of 106.4 MJ/m3 and self‐healing capability. Potential shielding materials for lightweight, wearable electronics, aerospace.

Decoding the role of bismuth oxide in advancing structural, thermal, and nuclear properties of [B2O3–Li2O–SiO2]-Nb2O5 glass systems

This paper investigates the pivotal role of bismuth oxide (Bi₂O₃) in the enhancement of nuclear safety, structural, and thermal properties of glasses, specifically in the BNLS system. BNLS system has the formula [B2O3–Li2O–SiO2]-Nb2O5(20-x)–(Bi2O3)x (where x = 0.0,5.0,10.0,15.0 and 20.0 mol%). Through a comparative study, the potential advantages, and limitations of integrating Bi₂O₃ in place of traditional elements are highlighted, emphasizing its importance in the field of advanced glass materials. FTIR analysis showed the presence of Bi–O vibrations of the tetrahedral [BO4] groups and the Bi–O–Bi linkages. DSC testified the glass formation with increasing thermal stability of the formed glass with the inclusion of Bi2O3 into the glass system. Through the quantification of the Gamma Linear Attenuation Coefficient (GLAC) and Gamma Mass Attenuation Coefficient (GMAC), the work identifies the attenuation behavior against varying photon energies. Notably, a concentration-dependent rise in attenuation characteristics is observed, with BNLS20 exhibiting the most potent radiation shielding. Glass Half-Value Layer (GHVL) parameters and Mass Gamma Photon Penetration (GMFP) were measured, reinforcing that glasses with higher Bi2O3 concentrations and lower GHVL are better attenuators. The transmission factor (ln(I/Io)) was also studied, confirming that BNLS20 possesses the most effective radiation shielding capabilities. This research establishes that adding Bi₂O₃ to the [B2O3–Li2O–SiO2]-Nb2O5 glass system markedly improves its thermal stability and radiation shielding capabilities. BNLS20, in particular, emerges as a standout for radiation protection, surpassing both other BNLS variants and conventional shielding materials, thereby positioning it as an exceptional choice for advanced nuclear safety applications.

Evaluation of shielding performance and light emission characteristics of luminescent radiation shields using Gd2O2S

ABSTRACT Gadolinium oxysulfide (Gd2O2S: GOS) has a large absorption cross-section for thermal neutrons and a mass density similar to that of iron used for shielding against X and γ-ray radiation. During GOS scintillator production process, its waste is also generated. If GOS waste can be used as an effective shielding material, it is worthwhile as beneficial use of the waste. We developed a novel radiation-shielding material using GOS waste. The developed shielding material can shield X, γ-rays and thermal neutrons more efficiently than conventional shielding materials and emit visible light due to leaked radiation when the shielding material is damaged, which subsequently be used to check the integrity of shielding using visible light. In this study, two types of shields, concrete and mortar with GOS as the aggregate and epoxy resin with GOS were prototyped and tested for radiation transmission. Results indicate that GOS shielding has a 10% higher shielding ability for X and γ-rays than heavy concrete with iron as aggregate. Additionally, the same shielding effect for thermal neutrons was attained at 1/10 the thickness of heavy concrete. Thus, using GOS waste is not only cost effective but also contributes to a circular economy.

Absorption‐Dominant Electromagnetic Interference (EMI) Shielding across Multiple mmWave Bands Using Conductive Patterned Magnetic Composite and Double‐Walled Carbon Nanotube Film

AbstractThe revolution of millimeter‐wave (mmWave) technologies is prompting a need for absorption‐dominant EMI shielding materials. While conventional shielding materials struggle in the mmWave spectrum due to their reflective nature, this study introduces a novel EMI shielding film with ultralow reflection (<0.05 dB or 1.5%), ultrahigh absorption (>70 dB or 98.5%), and superior shielding (>70 dB or 99.99999%) across triple mmWave frequency bands with a thickness of 400 µm. By integrating a magnetic composite layer (MCL), a conductive patterned grid (CPG), and a double‐walled carbon nanotube film (DWCNTF), specific resonant frequencies of electromagnetic waves are transmitted into the film with minimized reflection, and trapped and dissipated between the CPG and the DWCNTF. The design factors for resonant frequencies, such as the CPG geometry and the MCL refractive index, are systematically investigated based on electromagnetic wave propagation theories. This innovative approach presents a promising solution for effective mmWave EMI shielding materials, with implications for mobile communication, radar systems, and wireless gigabit communication.

A novel aloe vera mediated Bismuth–Magnesium–Copper nanocomposite for radiation shielding applications

In the current study, Bismuth-Magnesium-Copper nanocomposites (BMC NCs) are synthesized using versatile solution combustion synthesis using Alovera extract as a reducing agent. As obtained BMC NCs are characterized using standard techniques. Bragg’s reflections confirmed the formation of multi-phase BMC NCs with crystal sizes 18.11 nm and 21.12 nm. The surface morphology of BMC NCs confirmed the agglomeration of spherical-shaped nanoparticles. EDAX spectrum analyzed the presence of Bi, Mg, and Cu. The direct energy gap is found to be 3.08 eV. X-ray/gamma radiation shielding properties are then evaluated using a NaI(Tl) detector coupled with MCA. Shielding parameters are slightly higher than lead. Neutron shielding parameters are compared with conventional shielding materials. Scattering length is found to be 8.8 fm, and neutron absorption cross-section and neutron attenuation parameters of BMC NCs are found to be efficient when compared with lead, concrete, and steel. Bremsstrahlung radiation shielding parameters are computed at 1.511 MeV. Bremsstrahlung efficiency is comparable to lead, bremsstrahlung dose rate and specific bremsstrahlung constant are found to be more in comparison with lead. Thus, BMC NCs are highly efficient in shielding X/gamma ray and neutron radiations.

Effect of mixed rare earth cations on structure, optical, mechanical and radiation shielding parameters of Na2O–B2O3 glass

The value of rare earth-containing glasses continues to increase, resulting in a higher cost for producing such glasses. The reduction in rare earth content reduces the cost of the production process. Investigating whether it is possible to prepare glasses with low rare earth (such as Dy and Sm) contents is valuable. In this work, the impacts of Dy2O3/ Sm2O3 substitutions on borate glass's structural, optical, and mechanical features were investigated. The optical studies reflected the structural modifications. For example, Urbach tail increased from 0.39 to 0.69 eV with further Dy2O3/ Sm2O3 substitutions. This increasing behavior refers to a less stable glass matrix. This outcome was substantiated by the diminished values of all elastic parameters in the current glasses upon additional Dy2O3/ Sm2O3 substitutions. Nonlinear optical parameters were examined across various wavelengths and compositions, revealing negligible variations within the visible and near-infrared (Vis-NIR) spans. However, a notable decrease was observed in the UV region, exhibiting a rapid decline with increasing substitutions. Furthermore, induced defects within the internal structure of the glassy network, notably non-bridging oxygens with additional Dy2O3/ Sm2O3 substitution, resulted in heightened nonlinear optical parameters. Simultaneously, all elasticity moduli decreased with further Dy2O3 additions in the current glassy system, attributed to increased disorder caused by defect production, dangling bonds, and non-bridging oxygens in the glassy matrix.In addition, the half-value layers of all glass samples were compared to those of typical and widely used shielding materials. Through this analysis, certain glass samples demonstrated superior qualities compared to conventional shielding materials. Notably, the glass sample with the highest Sm2O3 level (and correspondingly the lowest Dy2O3 value) exhibited particularly favorable attributes. Consequently, our glass samples show potential as effective shields in nuclear radiation environments.

Synthesis and characterisation of lead-magnesium-boron nanocomposite for radiation shielding application.

There is a need for the replacement of toxic lead with nontoxic materials in radiation shielding applications. Instead of pure lead, lead mixed compounds/mixtures/alloys are considered to be less toxic and hence preferred for radiation shielding purposes. The compounds with magnesium are said to be having good magnetic and mechanical properties. Meanwhile, the boron element avoids secondary radiation and absorbs neutrons. The compound which is a mixture of lead, magnesium and boron is expected to be a good shielding material for radiation for X-rays/gamma rays. Hence in the present study, we have synthesised the lead-magnesium-boron (LMB) nanocomposites (NCs) using the green synthesis approach for the first time. LMB is synthesised by solution combustion method using Aloe vera as a reducing agent. The synthesised NCs are characterised using well-known characterisation techniques. Powder X-ray diffraction confirmed the formation of multi-phase LMB NCs, and average crystal size is found to be 13-15nm. Surface morphology and chemical composition are affirmed by SEM and EDX. The optical energy gap is found to be 1.87eV. FTIR confirmed the functional groups. X-rays/gamma rays, neutrons and bremsstrahlung radiation shielding efficiency are measured by experimental and theoretical, compared with conventional shielding materials. LMB NCs have proved to be efficient. Hence, LMB NCs proved to be potential in X-rays/gamma rays, neutrons and bremsstrahlung radiation shielding.

Comparative analysis of the effectiveness of natural polymers and conventional space radiation shielding polymers in spacecraft for prolonged space expeditions

This paper investigates the shielding effectiveness of natural polymers, such as natural rubber and cotton, against space radiation. The results are compared with those of conventional shielding materials, such as polyethylene, Kevlar, and polycarbonate. Monte Carlo simulations were performed using a Geant4-based tool, Multi-layered shielding simulation software (MULASSIS). The shielding properties were studied using proton, alpha, and iron ions with energies of 1 GeV n−1. Online Tool for the Assessment of Radiation in Space (OLTARIS) is used for calculating the effective dose equivalent for the GCR spectra. Both studies showed that the natural polymers are just as effective as conventional space radiation shielding materials in terms of dose reduction. Natural rubber is found to be the most effective among the natural polymers. For 50 g cm−2 aluminum with 20 g cm−2 layer of chosen materials configuration, the effective dose equivalent values (mSv/day) for Polyethylene, Kevlar, Polycarbonate, Kapton, Epoxy, Dacron, and Vectran were 0.93, 1.08, 0.995, 1.056, 1.007, 1.031, and 1.042, respectively. The effective dose equivalent values (mSv/day) for natural polymers (natural rubber, cotton, jute, and silk) under the same conditions were 0.95, 1.004, 1.036, and 1.004, respectively. The challenges of utilizing radiation shields made of natural polymers are also briefly covered.

CoCrFeNiSi high entropy alloy: Synthesis, structural and radiation shielding properties

High entropy alloys (HEAs) have emerged as a distinct class of alloys with unique design strategies, different from traditional alloys. These alloys hold great promise for diverse applications, and the investigation of their nuclear radiation shielding properties has become an important and emerging area of research. In this experimental study, an equimolar CoCrFeNiSi HEA was prepared using the ball milling method. The focus was on characterizing the crystalline structure, morphological features, and radiation shielding properties of the synthesized HEA. X-ray diffraction analysis revealed that the HEA exhibited a face-centered cubic (FCC) phase structure. The crystallite size was significantly reduced from 23.63 nm to 3.22 nm, indicating the refinement of the microstructure. The homogeneity of the alloy was confirmed through scanning electron microscopy with energy-dispersive X-ray spectroscopy (SEM-EDX), which showed that the five elements were uniformly distributed within the powder alloy. To evaluate the radiation shielding properties, linear attenuation coefficients (LAC) of the CoCrFeNiSi HEA powder were measured using a 662 keV gamma source and a NaI(Tl) detector system (ORTEC® 905–4). The experimental LAC values were determined to be 0.2140 ± 0.01 cm⁻1. Theoretical calculations using MCNP6.2 and XCOM code were also performed and showed good agreement with the experimental results. Comparing the CoCrFeNiSi HEA with common shield materials such as thin films, glass systems, and some composites, it was found that the HEA outperformed them in terms of radiation shielding effectiveness. This demonstrates the potential of the CoCrFeNiSi HEA as an advanced alternative to conventional shielding materials, with potential applications in various fields.

A theoretical focus on nanoparticle attenuation capabilities for potential utilizations in radiation protect: TiO2-SiO2-Fe3O4-B4C-Al2O3

Radiation shielding materials are essential for various applications in space exploration, nuclear power plants, and medical devices. In this study, we present a theoretical design of radiation shielding nanocomposites based on a combination of TiO2-SiO2-Fe3O4-B4C-Al2O3 materials. Using the Phy-X/PSD, EpiXS, and XMuDAT programs, we calculated the radiation shielding properties, including mass attenuation coefficient, mean free path, and effective atomic number, of a series of nanocomposite structures with different Fe3O4 and B4C contents. Our results show that the addition of Fe3O4 and B4C to nanocomposites enhances the radiation shielding efficiency and the maximum shielding is observed in the nanocomposite with the highest density. The theoretical calculations also reveal that the proposed nanocomposites have excellent radiation shielding properties compared to conventional shielding materials, such as lead and concrete. This work demonstrates the potential of using a computational approach to design novel radiation shielding nanocomposites with improved performance, which could have significant implications for a wide range of applications.

Li2B4O7–Bi2O3–ZrO4–CaWO4 glass system for neutron protection in neutron applications

In this study, new glass samples with a chemical composition of 40Li2B4O7+xBi2O3+(55–x)ZrO4+5CaWO4 (x = 10, 20, 30, 40, and 50 wt%) were fabricated using the melt quenching-annealing technique. Important neutron shielding parameters, such as the effective neutron removal cross-section, half-value layer, and neutron transmission factor, of all the new glass samples were calculated using the GEANT4 Monte Carlo simulation code. In addition, neutron dose measurements were performed using an 241Am–Be fast neutron source with an activity of 74 GBq and an average neutron energy of 4.5 MeV and a BF3 gaseous neutron detector. The results were compared with those of conventional shielding materials to determine the neutron absorption capabilities of the new glass materials. All the new glass samples were found to have excellent neutron shielding abilities. In particular, the GB5 sample had a high absorption capacity compared to the other samples. These new glass samples may be used as shielding materials in various radiation applications, such as generation of nuclear energy, radiation medicine, and the transport and storage of radioactive wastes.

Tb3+-doped GeO2-B2O3–P2O5–ZnO magneto-optical glasses: Potential application as gamma-radiation absorbers

Radiation interaction parameters are important for exploring the technological relevance of materials in radiation environments. In this research paper, gamma-ray shielding efficacy of GeO2+B2O3+P2O5+ZnO magneto-optical glasses doped with Tb3+ and coded as GBPZT1-6 for Tb3+ doping concentrations ranging from 20 to 45 mol%, with a 5-mol% increment was investigated using theoretical and Monte Carlo simulation methods. The PHITS code and the Phy-X/PSD software was used to compute the mass attenuation coefficient (MAC) and other interaction quantities of the glasses for 0.015–15 MeV photons. Both methods' MAC data agree to within 2.90% of each other. At 0.015 MeV, the value of MAC is 59.9674 cm2/g, 64.1777 cm2/g, 67.6697 cm2/g, 70.6128 cm2/g, 73.1271 cm2/g and 75.2998 cm2/g for GBPZT1, GBPZT2, GBPZT3, GBPZT4, GBPZT5 and GBPZT6, respectively. The linear attenuation coefficients of the GBPZT glasses changed from 0.1340 to 247.5640 cm−1, 0.1490 to 286.8040 cm−1, 0.1650 to 326.6350 cm−1, 0.1790 to 365.7810 cm−1, 0.1990 to 413.9290 cm−1, and 0.2190 to 463.9450 cm−1 for GBPZT1, GBPZT2, GBPZT3, GBPZT4, GBPZT5, and GBPZT6. Comparatively, the photon attenuation abilities increase linearly as the density and Tb2O3 content of the glass system increased. Hence, GBPZT6 has the highest mass and linear attenuation coefficients, while GBPZT1 has the least. The BPZT glasses have better photon absorbing capacities compared to ordinary concrete and some other conventional shielding materials, thus making them attractive choice in radiation protection functions.

Radiation shielding performance of a borate-based glass system doped with bismuth oxide

Proper shielding against radiation emitted by commonly used isotopes is essential in various medical, industrial, and nuclear facilities. In this study, we focus on the nuclear security and the radiation shielding against fast-neutrons, gamma-rays, and charged particles attenuation properties of the borate glasses containing zinc, bismuth, and lithium (as modifier) according to the chemical form of xBi2O3+ (25-x)Li2O+ 60B2O3+ 15ZnO, where x is varying from 0 to 20 mol%. The fundamental parameters related to gamma-shielding (e.g. attenuation and transmission factors) were investigated via FLUKA simulations for specific energies namely 0.511 and 1.275 MeV emitted by 22Na isotope, and 0.365, 0.637, 0.284, and 0.723 MeV emitted by 131I isotope. The influence of the systematic substitution of Bi2O3 by Li2O on the shielding properties was discussed in detail for gamma, neutron, and charged particles. In addition, comparative studies were also performed between the current borate glasses and the standard conventional shielding materials. The results of the present study indicate that the lowest MFP (HVL) occurred at 0.284 MeV (energy emitted by 22Na isotope) with the values (in the unit of cm) of 3.54 (2.45), 2.86 (1.98), 1.12 (0.78), 0.91 (0.63), and 0.72 (0.49) cm for the borate glasses of BLBZ1, BLBZ2, BLBZ3, BLBZ4, and BLBZ5, respectively. It was also observed that the maximum ℜ of BLBZ1 was seen at 1.3 MeV with the values of 2663.6, 19.3, 3.6, and 1.7 μm for the charged particles of an electron, proton, alpha particle, and carbon ion, respectively. This suggests that the BLBZ5 sample has a potential use in radiation shielding applications for superior nuclear security.

Radiation Shielding Parameters for Zinc Borate and Zinc Silicate Glasses Doped with Oxides of Bismuth -A Comparative Study

In the present work borate and silicate glass systems containing oxides of zinc and bismuth are explored as potential candidates for the radiation shielding applications. NIST XCOM computer program is employed for the estimations of mass attenuation and half value layer at different photon energy values ranging from 10-3MeV to 105 MeV. To get the idea regarding thickness of the glass material required to decrease the intensity of gamma ray photons to 50% of its starting value, the values of half value layer are analysed. Physical parameters like molar volume and density measurements are conducted to get insight of glass structure. The results obtained are compared with conventional shielding materials like concretes. The present work shows that the reports glasses in the present study are quite useful for radiation shielding purpose.

Epoxy-based Light Weight Gamma Ray Shielding Materials

Lightweight epoxy-based X-ray /gamma-ray shielding materials were synthesized by blending epoxy resin with the different weight percent of lead oxide, bismuth oxide, and tungsten oxide powders. The synthesized composites were characterized using FTIR, elemental analyzer, and X-ray radiography for their chemical structure, elemental composition, and filler distribution. The photon interaction parameters such as linear/mass attenuation coefficient, attenuation percentage, and half value layer were determined for all composites at photon energies 59.5, 364, and 661.7 keV. The measured mass attenuation coefficients of epoxy composites matched well with the obtained from XCOM. Moreover, the shielding effectiveness of the composites was analyzed by the half-value layer and heaviness of the composites and was compared with conventional shielding materials (concrete, lead, and steel).

Gamma radiation shielding studies on highly dense barium bismuth borate glasses

AbstractTransparent dense barium bismuth borate (BBB) glasses in ternary x(BaO–Bi2O3)–(1–x)B2O3 system, with x = .15, .25, .35, and .45, were prepared by the melt‐quenching process. Density of the glasses increased to 7.145 g/cm3 with increasing BaO–Bi2O3 content. Gamma radiation shielding performance of the glasses was estimated by studying mass attenuation coefficients (MAC) and effective atomic numbers, using XCOM software as a function of photon energy. Subsequently, experimental MAC values of the glasses were measured using 152Eu and 60Co sources by the radiation transmission method. Measured and calculated MAC values of the glasses were in close agreement. Equivalent atomic numbers, exposure, and energy absorption buildup factors were analyzed at different mean free paths and photon energies using Phy‐X software. Dense glasses exhibited large effective atomic numbers and radiation shielding characteristics comparable with the dense heavy metal oxide glasses. Effective atomic numbers of the glasses were found to be close to the heavy metallic elements (Pb, W, and Hf) at low gamma energies. Radiation shielding ability of the glasses is discussed by comparing with the recently reported radiation shielding glasses and conventional shielding materials. Lead‐free and dense transparent BBB glasses in the present study can be effective in radiation shielding for radiological applications.

Significant influence of Cu content on the radiation shielding properties of Ge-Se-Te bulk glasses

Bulk metallic glasses have attracted significant attention from researchers and material engineers for several applications. In this paper, we study the influence of Cu content on the radiation shielding properties xCu-(20-x)Ge-40Se–40Te (0 < x ≤ 20 at.%) bulk glasses. These bulk glassy samples are designed by utilizing FLUKA Monte Carlo based on their densities and chemical compositions. For x- and gamma-rays shielding studies, the mass attenuation coefficients (μ/ρ) of the bulk glasses are obtained via photon beam transmission experiment performed based on FLUKA simulations. Furthermore, we evaluate the shielding characteristics of the involved glassy specimens against charged particles and neutrons beam. The obtained findings show that the trend of μ follows the pattern: CGST1 < CGST2 < CGST3 < CGST4 < CGST5 for x = 0, 5, 10, 15, and 20, respectively. However, this trend is more conspicuous in the photoelectric effect dominated energies due to the greater dependence of μpe on the Z of the glasses. The present glassy samples show superior photon absorption capacity, especially CSGT5 sample, as compared to conventional shielding materials. Therefore, they can be deployed for nuclear shielding applications in space and other radiation environments.

Investigations on physical, structural and nuclear radiation shielding behaviour of niobium–bismuth–cadmium–zinc borate glass system

In the present paper, glass sample with the chemical composition xNb2O5+0.20Bi2O3+0.20CdO+0.10ZnO+ (0.50-x)B2O3 (where x = 0.05, 0.10, 0.15, 0.20, 0.25 mol fraction) were prepared by melt quenching-annealing technique. The density, molar volume, oxygen molar volume (OMV) of the glass samples are found to increase increases from 5.35 to 5.65 gcm−3, 32.69–37.32 cm3/mole, 14.323–14336 cm3/mole, respectively, with the increase in molar concentration of Niobium pentoxide. The value of Poisson's ratio shows a very small variation in the range of 0.240–0.247 for the present glass matrix, however these results confirms that the prepared glass samples have high cross link density. The linear attenuation coefficients were measured experimentally by employing narrow beam transmission geometry (total scatter acceptance angle = 2.22°) with NaI(Tl) spectroscopy in the gamma photon energy range of 59.54–1332 keV. These values of linear attenuation coefficient were then further used to calculate other attenuation parameters namely Half Value Layer (HVL), Radiation Protection Efficiency (RPE), Mass Attenuation Coefficient (MAC), effective atomic number (Zeff), electron density (Ne) and Buildup Factor (BF). Measured values of attenuation parameters have also been compared the values obtained theoretically using online software Phy-X/PSD and Py-MLBUF as well as with values obtained through FLUKA (Monte-Carlo) simulations code. Excellent agreements have been observed between experimental, theoretical and simulation results for the prepared glass samples. In addition to this, fast neutron removal cross sections (∑R cm−1) were calculated for the glass matrix under investigations. On the basis of the obtained results, it has been reported that the prepared glass samples possess superior shielding efficiency against gamma rays and fast neutrons as compared to conventional shielding materials.

MIKE: a new computational tool for investigating radiation, optical and physical properties of prototyped shielding materials

The development of new, advanced shielding materials has attracted great interest among scientists and engineers. Recently, various shielding materials have been developed, which could replace the toxic, heavy, and costly conventional shielding materials. In this paper, we present our new computational software, MIKE, to assist researchers in the process of calculating and analyzing different radiation shielding parameters, such as the linear attenuation coefficient, mass attenuation coefficient, and half-value layer. The shielding parameter equations were coded using MATLAB. Additionally, the computational tool can be used to calculate the physical and optical properties of the selected composition, such as the average molar weight, molar volume, and molar electronic polarizability. Moreover, this tool allows the user to analyze the shielding parameters and the transmission factors for a selected material against a wide range of ionizing radiation energies. The newly developed computational software has been compared with existing radiation-shielding codes, including Phy-X/PSD and WinXcom, in addition to the available experimental data in the literature. The computed values produced using the MIKE software show good agreement with values calculated using the available competitor software programs (WinXcom, Phy-X/PSD, and the Monte Carlo method) with percentage differences of less than 0.2%. Our user-friendly computational software could help researchers evaluate whether various shielding materials meet the requirements of radiation applications, such as diagnostic and therapy applications including mammography, general radiography, computed tomography (CT), nuclear medicine, and high-energy photons used in radiotherapy applications.