Gamma Radiation Shielding Research Articles

Investigation of the mechanical properties, shielding parameters and flux distribution in borate - Based glass system using PHITS code; a simulation study

A descriptive method for the attenuation and spatial distribution of flux of photons and fast neutrons for 20Bi2O3 − xPbO − (80 − 2x) B2O3 − xGeO2 (x = 5, 10, 20 and 30 mol %) glass systems (coded as S1, S2, S3, S4 respectively) were performed using PHITS code. The calculated elastic moduli, Young modulus, EM was ranged between 32.58 and 33.81 GPa, while bulk KM and shear GM moduli were in the range of 23.36–30.45 and 12.32–13.15 GPa, respectively. However longitudinal modulus LM was between 40.89 and 46.89 GPa. The spatial distribution of the transmitted photon flux showed a decrease with increasing Pb and Ge concentrations. The mass attenuation coefficients, μm were found to be 70.755–0.042, 76.160–0.043, 83.378–0.046 and 91.895–0.047 cm2/g for S1, S2, S3 and S4 respectively in the energy range of 0.015–15 MeV. The Half Value Layer (HVL) and mean free path (MFP) values were registered in the order of S4 < S3 < S2 < S1. At low energy, the exposure buildup factor EBF of the glasses recorded decrease by the substitution of B2O3 by PbO and GeO2 contents. At energy 0.15 MeV, a crossed behavior was noticed. However, at high energy the inverse behavior of EBF was observed. The neutron transmitted flux percentages, at thickness 10 cm were in the range of 10.26–15.51% at all the selected energies. The linear absorption coefficients ΣT, ranged between 0.220 and 0.278 cm−1 which indicated that S4 represents the best shielding capacity among all. The overall results of this work assessed the selected glasses potential for use as gamma and fast neutron radiation shielding products.

Determination of Gamma Radiation Shielding Characteristics for Some Iron-Based Metallic Glasses

In this study, the gamma radiation shielding characteristics of metallic glasses having Fe81B13.5Si3.5C2, Fe79B16Si5, Fe78B13Si9 and Fe40Ni38B18Mo4 components and coded as FeBSiC, FeBSi1, FeBSi2 and FeNiBMo were investigated. In order to investigate, the mass attenuation coefficients for metallic glasses in the photon energies range of 0.060 to 2.614 MeV were calculated with the help of WinXCOM program and GEANT4 and FLUKA simulation codes. The linear attenuation coefficient, half and tenth value layers, mean free path, effective atomic number and electron density parameters were calculated with the help of the calculated mass attenuation coefficients. Variations of the calculated gamma radiation shielding parameters with photon energy were discussed. It was observed that mass and linear attenuation coefficients, effective atomic number and electron density parameters decreased with increasing photon energy, while half and tenth value layers and mean free path parameters increased with increasing photon energy. It has been observed that metallic glasses have better gamma shielding capabilities in the low photon energy region, and metallic glass coded as FeNiBMo has better gamma radiation shielding capacity than other studied metallic glasses.

Effect of sodium oxide (Na2O) glass modifier on physical properties and gamma shielding in tellurite glass systems TeO2-ZnO-PbO-Bi2O3 (TZPB)

&lt;span&gt;TZPB glasses with the composition &lt;/span&gt;&lt;span&gt;55TeO&lt;sub&gt;2&lt;/sub&gt;-(41-x)ZnO-2Bi&lt;sub&gt;2&lt;/sub&gt;O&lt;sub&gt;3&lt;/sub&gt;-2PbO-xNa&lt;sub&gt;2&lt;/sub&gt;O &lt;/span&gt;&lt;span&gt;(x= 2; 2.5; 3; 3.5 mol%) have been fabricated and characterized to determine the physical properties and gamma radiation shielding parameters. The method of glass fabrication is melt quenching with the holding temperature at 900˚C for 30 minutes and the annealing temperature at 256˚C for 6 hours. The result of the characterization of the density and gamma shielding parameters was calculated using Phy-X PSD software. The glass density was measured using Archimedes's principle and showed a decrease from 5.79 to 5.73 g/cm&lt;sup&gt;3&lt;/sup&gt;. The molar volume increased from 23.3 to 23.6 g/mol with the addition of Na&lt;sub&gt;2&lt;/sub&gt;O concentration. Gamma radiation shielding parameters, LAC, MAC, MFP, HVL, and TVL simulated with the energy range were 10&lt;sup&gt;-3&lt;/sup&gt;-10&lt;sup&gt;5&lt;/sup&gt; MeV. The results of Phy-X/PSD software showed an increasing MAC, MFP, HVL, and TVL and decreasing in LAC with an increase in Na&lt;sub&gt;2&lt;/sub&gt;O concentration.&lt;/span&gt;

Characterization and applications of highly optical transparency tellurite glasses doped with Er3+, Tm3+, and Nd3+

Highly optical transparent tellurite glasses are attractive and viable as alternative materials for absorbing gamma-ray photons in the design of radiation protection structures. This report examines the potential of new tellurite glass systems (TeO2-ZnO-WO3-Bi2O3) doped with Er3+ (TZWB-Er), Tm3+ (TZWB-Tm), and Nd3+ (TZWB-Nd) as shielding materials against charged and uncharged radiation. The mass attenuation coefficient, μ/ρ of the glasses was computed by XCOM software and data from simulations of photon transmission in the PHIT code. The total stopping powers and range of beta particles β, H+, He2+, and C6+ in the glasses were estimated by ESTAR, PSTAR, ASTAR, and SRIM software at particle kinetic energies within 0.1–10 MeV. The fast neutron (FN) removal and thermal neutron absorption cross-sections in the glasses were also computed. The stopping powers and ranges of the considered charged particles showed variations that depended on the kinetic energy of the particles and chemical composition of the glasses. The TZWB-M glasses are better alternatives as gamma-radiation shields compared to traditional shielding substances such as concrete, some commercial glass shields, and recently recommended glass shields. The glasses are thus recommended for the design of radiation safety structures.

A detailed investigation of gamma and neutron shielding capabilities of ternary composites doped with polyacrylonitrile and gadolinium (III) sulfate

The shielding efficiencies of gamma and neutron radiations for ternary composites containing polyester resin, polyacrylonitrile and gadolinium (III) sulfate at different ratios were investigated in the present study. In order to investigate the gamma radiation shielding capacity of the produced ternary composites, linear and mass attenuation coefficients, half value layer, effective atomic number and radiation protection efficiency parameters were determined experimentally, theoretically and using the GEANT4 simulation code. The gamma shielding capabilities of the composites were studied in the photon energy range of 59.5–1332.5 keV. In order to investigate the neutron shielding abilities of composites, inelastic, elastic, capture and transport numbers, total macroscopic cross section and mean free path parameters were determined with the help of GEANT4 simulation code. In addition, the number of transmitted neutrons at different sample thicknesses and neutron energies were also determined. It was observed that gamma radiation shielding properties were improved due to the increasing amount of gadolinium (III) sulfate and neutron shielding properties were improved due to the increasing amount of polyacrylonitrile. While the composite coded P0Gd50 exhibits a better gamma radiation shielding ability than the others, the neutron shielding of the sample coded P50Gd0 is also more favorable than the others.

Evaluation of the radiation shielding properties of ornamental rocks produced in Brazil: A Monte Carlo approach

In this work, the Monte Carlo MCNPX (2.7.0) code was used to evaluate the radioprotective properties of ten ornamental granitic samples produced in Brazil. For each sample of granite, the mass attenuation coefficient (µ/ρ) and half-value layer (HVL) were evaluated using the photon energy emitted by the following radioisotopes: 241Am (59,5 keV), 133Ba (356 keV), 137Cs (662 keV), 60Co (1250 keV), and 22Na (1274 keV). The MCNPX results showed agreement with the values obtained by using the XCOM database, as well as with theoretical and experimental results, available on the literature. The computational model built in this work can be used by the scientific community interested in parameters involving new materials for gamma radiation shielding, which has been used in different areas of the nuclear sciences.

Investigation of gamma radiation shielding characteristics of bismuth reinforced ternary composites in wide photon energy region

The aim of this study is to evaluate gamma ray shielding properties for bismuth doped barite-based ternary polymer composite materials. In the first stage of the study, a polymer matrix was prepared by combining orthophthalic unsaturated polyester resin (OUP), Methyl Ethyl Ketone Peroxide (MEKP) and Cobalt Octoate (6%) (Co-6). Then, barite and bismuth were added in certain proportions as filler material into this polymer matrix and thus ternary composites were produced. Experimental studies for the produced samples were carried out in narrow beam geometry using HPGe detector and 133Ba, 22Na, 137Cs, 60Co radioactive sources which emit photons between 276.4 and 1332.5 keV energy. To determine the gamma ray shielding properties of the produced ternary composites, radiation protection efficiency (RPE), linear attenuation coefficient (μ), mass attenuation coefficient (μ/ρ), half value layer (HVL), tenth value layer (TVL), mean free path (MFP), effective atomic number (Zeff), effective electron density (NE) parameters were obtained. Experimental results were compared with theoretical results obtained with WinXCOM software and GEANT4 Monte Carlo simulation code. Experimental and theoretical results were found to be compatible with each other. According to obtained results, it was found that the sample with the best shielding property among the prepared samples was BaBi50 coded sample.

Investigation of the Effect of PbO Doping on Telluride Glass Ceramics as a Potential Material for Gamma Radiation Shielding.

The purpose of this paper is to study the effect of PbO doping of multicomponent composite glass-like ceramics based on TeO2, WO3, Bi2O3, MoO3, and SiO2, which are one of the promising materials for gamma radiation shielding. According to X-ray diffraction data, it was found that the PbO dopant concentration increase from 0.10 to 0.20-0.25 mol results in the initialization of the phase transformation and structural ordering processes, which are expressed in the formation of SiO2 and PbWO4 phases, and the crystallinity degree growth. An analysis of the optical properties showed that a change in the ratio of the contributions of the amorphous and ordered fractions leads to the optical density increase and the band gap alteration, as well as a variation in the optical characteristics. During the study of the strength and mechanical properties of the synthesized ceramics, depending on the dopant concentration, it was found that when inclusions in the form of PbWO4 are formed in the structure, the strength characteristics increase by 70-80% compared to the initial data, which indicates the doping efficiency and a rise in the mechanical strength of ceramics to external influences. During evaluation of the shielding protective characteristics of the synthesized ceramics, it was revealed that the formation of PbWO4 in the structure results in a rise in the high-energy gamma ray absorption efficiency.

Evaluation of the gamma radiation shielding characteristics of epoxy wall paint modified with micro sized Bi2O3 and WO3

Evaluation of the gamma radiation shielding characteristics of epoxy wall paint modified with micro sized Bi2O3 and WO3

Assessment of the Usability of a Composite Containing Boron Carbide for Shielding the Gamma Rays

Considering the negative effects on the environment and toxicity of lead, which has been widely used for gamma shielding for a long time in nuclear technology, studies have been focused on the development of various materials that can be used as an alternative to lead in gamma radiation shielding. In this research, a composite material containing magnetite and boron carbide (epoxy/magnetite/boron carbide) and gamma transmission technique which is emphasized in nuclear applications have been used for the study of gamma ray shielding. The radiation sources considered for this technique are the radioisotopes Am-241, Cs-137, Na-22 and Co-60, which are important in nuclear technology. The interactions between the composite material and gammas with 59.5, 511, 661.6, 1173.2, 1274.5 and 1332.5 keV energies were investigated separately by the Monte Carlo method, and the ability of the material to shield the radiations at these energies was investigated. Gamma rays, one by one, followed by using cross sections and determining the probability of interaction with the composite from the point they are emitted until they leave the system (through escaping or absorption from the system) in the Monte Carlo code, which is written to determine the linear attenuation coefficient, mean free path, half value layer and tenth value layer, among the radiation shielding parameters of the composite under investigation. The shielding parameters calculated using the simulation results were also calculated using the data obtained from the XCOM software, and the results were found to be compatible with each other. On the other hand, in order to better evaluate the usability of the composite as an alternative shielding material for nuclear applications in the studied energy range, a comparison was made with the shielding parameters of various materials available in the literature.

Assessment on gamma radiation shielding properties of molybdenum doped bricks

Gamma radiation permeability experiments were carried out by preparing a new type of brick mixture with Molybdenum (Mo, Z = 42) additives (0 (B0), 5 (B1), 10 (B2), 20 (B3), 30 (B4), 40 (B5), 50 (B6) %wt). The density of the bricks increased to 2.79 g/cm3 with increasing Mo content. The bricks were exposed to gamma rays with 81, 276, 303, 356 and 383 keV photon energies emitted from 133Ba radioactive source and the transmitted intensities were detected using the Canberra Ultra Ge detector. Gamma attenuation characteristics of the bricks were also calculated by mass attenuation coefficients, effective atomic numbers and electron densities using the EpiXS program as a function of gamma-ray energy. And also, the exposure and energy absorption buildup factors of bricks were determined at different mean-free paths and photon energies using EpiXS program. It was observed that as the density of the bricks increased, the radiation shielding properties also increased. The values of the mass attenuation coefficients at 81 keV for B0–B6 bricks were found to vary between 0.229 and 1.08 cm2/g. It was found that Zeff values were 13.3, 16.1, 17.4, 19.09, 22.5, 25.3 and 26.6 for B0, B1, B2, B3, B4, B5 and B6 samples at 81 keV, respectively. As can be seen from these results, B6 brick has the highest Zeff value. And also, the calculated results displayed that the lowest values of exposure buildup factors and energy absorption buildup factors are observed for the B6 brick. The B6 brick containing 50% Mo element has a higher mass attenuation coefficient and effective atomic number values than the other bricks. The values of exposure and energy absorption buildup factors of B6 brick were lower than the values of other investigated samples. The measured and calculated shielding values of the bricks were in close agreement. It has been seen that the shielding results of these new types of bricks, which are low in cost and easy to produce and use, are quite successful.

Effect of WO3 on the radiation shielding ability of TeO2–TiO2–WO3 glass system

Abstract In this study, glass composition based on tungsten oxide (WO3) doped tellurium, titanium glasses: (100 − x − y) TeO2–xTiO2–yWO3: where (x = 5) and (y = 5, 10, 15, 20, 25) coded as TT5W5, TT5W10, TT5W15, TT5W20, and TT5W25 were investigated for shielding properties against ionizing radiation. Gamma radiation shielding parameters such as mass attenuation coefficients (MAC) are calculated through MCNPx code and Phy-X/PSD software in the energy range of 0.015–15 MeV. Obtained MAC values are then used to calculate other gamma radiation shielding parameters such as mean free path (MFP) and effective atomic number (Z eff). Besides this, the exposure buildup factor (EBF) was also calculated by using EXABCal software at different penetration depths (PDs) in the energy range of 0.015–15 MeV. Sample TT5W25, which has a larger WO3 content of 25 mol% shows higher values of MAC and lower values of MFP among all the examined glass samples. Our investigated TeO2–TiO2–WO3 glass samples possess the lowest MFP values in comparison with the different types of concretes and commercially available shielding glasses. In addition, fast neutron shielding characteristics in light of fast neutron removal cross-section have also been computed. Glass sample TT5W25 possesses the higher values of fast neutron removal cross-section as compared to the other glass samples. The results indicate that the adding up of WO3 improves shielding against the fast neutron and gamma radiation.

Monte Carlo Investigation of Gamma Radiation Shielding Features for Bi2O3/Epoxy Composites

Three different samples were synthesized based on polyepoxide resin, a solidifying agent, and a Bi2O3 doping compound. The polyepoxide resin and solidifying agent were added in a 2:1 ratio by weight and the Bi2O3 compound was added in ratios of 0, 5, and 10 wt. %. The density of the synthesized composites was measured using an MH-300A densimeter with an uncertainty in measurement of 0.001 g/cm3. The measurements showed that the density of the fabricated composite varied from 1.103 g/cm3 to 1.20 g/cm3 when the reinforcing Bi2O3 compound was raised from 0 wt. % to 10 wt. %. Furthermore, the γ-ray shielding parameters were evaluated based on the simulated mean track length of γ-photons inside the synthesized composites using MCNP-5 code. The simulated results show an enhancement in the shielding parameter when increasing the Bi2O3 concentration, where the linear attenuation coefficient values increased from 0.101 cm−1 to 0.118 cm−1 as the Bi2O3 concentration increased from 0 to 10 wt. %. The increase in the LAC has a positive effect on the other shielding properties.

Evaluation of gamma and neutron radiation shielding properties of the GGBFS based geopolymer concrete

Superior characteristics of the ground granulated blast furnace slag (GGBFS) based geopolymer concrete (GGC) compared with the ordinary Portland cement (OPC)-based concrete (OPCC), have made it a more preferable choice for being used in the radiation shielding. The aim of this study is to investigate the radiation shielding properties of the GGC containing different contents of magnetite aggregates in separate and cover-layer forms. In this study: 1)gamma and neutron attenuation capacities of one-layer samples, including the OPCC containing 100 % normal-density aggregates, the GGC containing 0 % to 100 % magnetite aggregates and the steel fiber reinforced GGC containing 100 % magnetite aggregates have been evaluated, 2)the OPCC containing 100 % normal-density aggregates specimens have been covered with 5 cm layer of the concretes studied at the first stage to investigate their effects on radiation attenuation and 3)a comparison between a two-layer specimen and an equivalent mixed sample has been conducted. The main results obtained are: a)when the ordinary aggregates are replaced by the magnetite ones from 0 to 100 volume percentages, the parameters such as the linear attenuation coefficient (μ) and the removal cross section (ΣR) are respectively increased from 0.14225 to 0.18055 cm−1 and from 0.116086 to 0.143864 cm−1 in the GGC, b)adding 1.5 vol% of steel fibers to the GGC containing 100 % magnetite aggregates leads to increase in μ and ΣR respectively equal to 2.697 % and 6.5819 %, c)for gamma radiation, ratios of the transmitted rays to the incident ones in sample covered with the GGC containing 100 % magnetite aggregates and the specimen covered with the GGC containing 100 % ordinary aggregates have been obtained respectively equal to 0.197563 and 0.250297. For neutron radiation, these ratios have been obtained equal to 0.261019 and 0.346008, respectively and d)radiation attenuation capacity of the two-layer specimen has been obtained higher than that of its equivalent mixed sample.

DMSO-Bismuth polymer composite as gamma radiation shield – A computational study

The present study deals with investigating several shielding parameters of Dimethyl Sulfoxide (DMSO) with varying concentration of bismuth as a filler. Exhaustive work has been done in finding the best shielding material from a multitude of materials, composites, glasses etc., by using multiple methods of study. In this study the chosen composites were explored by using the computational method of finding the shielding parameters, which are an important guide in establishing if the material selected can be a shielding material and whether it is a good option as well. The parameters computed for this study are linear attenuation and mass attenuation coefficient, half value layer (HVL), tenth value layer (TVL), mean free path (mfp), effective atomic number, effective electron density and the build-up factors for the said composites using XCOM, XMuDAT and PhyX. Upon obtaining the parameters of these composites and detailed analysis, it is observed that the attenuation coefficient increases with increase in bismuth content and the composite with 90% Bismuth showed the best results in terms of shielding. To understand the efficiency of these shielding materials, they were compared with Lead and Barite which are considered as the traditional shielding materials. From these comparisons, it is seen that 10%DMSO + 90%Bismuth is an ideal candidate for shielding of gamma rays and also proves to be light weight in contrast to the standard shielding materials.

Enhanced wide energy regions gamma ray shielding property for Bi2O3-Gd2O(CO3)2∙H2O/EP composites with strong electron cloud overlap

With the complexity of the radiation environment and the increased demand for radiation protection, there is an urgent need for high-performance and wide-energy range gamma ray shielding materials. Bi2O3 has excellent gamma ray shielding properties, while Bi exhibits weak shielding performance of low-energy gamma rays in the range of 36.4–90.5 keV. In this work, a two-step hydrothermal strategy was proposed for Bi2O3-Gd2O(CO3)2∙H2O heterostructure (h-BG) to achieve effective shielding of the materials of low-energy gamma radiation. Bi2O3-Gd2O(CO3)2∙H2O/EP-30 composite has excellent shielding performance against low, medium, and high energy gamma radiation. In addition, the shielding performance of the Bi2O3-Gd2O(CO3)2∙H2O/EP-30 composites proved to be superior to some materials in the literature of 59.5 keV. Furthermore, simulations with the Phy-X/PSD program demonstrate that Gd2O(CO3)2∙H2O combined with Bi2O3 is an adequate method for achieving gamma radiation shielding in a wide energy region. The differential charge density calculations suggest that the formation of a heterogeneous interface between Bi2O3 and Gd2O(CO3)2∙H2O leads to an overlap of the interfacial electron cloud, which increases the probability of collision between the rays and the electrons. This is an essential reason for the enhanced gamma shielding property. This work could serve as a new strategy for the design of gamma radiation shielding materials.

Simulation of neutron and gamma radiation shielding properties of KNN-LMN lead-free relaxor ceramics

Simulation of neutron and gamma radiation shielding properties of KNN-LMN lead-free relaxor ceramics

Polylactic acid tungsten trioxide reinforced composites: A study of their thermal, optical, and gamma radiation attenuation performance

In the current investigation, the gamma radiation shielding abilities, structure, and thermal and optical properties of Polylactic acid PLA have been tried to be developed by introducing tungsten trioxide WO3. PLA/WO3 composites were fabricated by a solution mixing method at different weights percent (1%, 3%, 5%, and 7%). SEM indicates the good dispersion of WO3 in the PLA matrix, and the X-ray diffraction (XRD) pattern displays the existence of recognizable peaks for PLA and WO3. The thermal properties were investigated by thermo-gravimetric analysis (TGA), which enhances the thermal stability of the PLA/WO3 composites more than pure PLA. The transmittance decreases with increasing the WO3 content in the PLA matrix while the absorption and extinction coefficients α and k as well as the refractive index, rise with the increase of the WO3 content in the PLA matrix. The radiation shielding parameters have been experimentally reported. The equipment used in the experiment consisted of a NaI detector as well as a variety of radioactive point sources that released photons with energy of 80, 238, 356, 662, 1173, 1333, and 2164 keV, respectively. Examining the linear attenuation coefficient (μ), the half-value layer (T0.5), and the radiation protection effectiveness of the PLA/WO3 composites was done in order to investigate the gamma radiation shielding capabilities of the materials (RPE). Pure PLA (free WO3) was found to have the lowest μ values, and it was discovered that increasing the WO3 content led to an improvement in the photon attenuation competency of the present epoxy. The T0.5 lengths of the PLA/WO3 composites were lowered when WO3 was added. This verified that adding WO3 increases the radiation absorption capabilities of the PLA/WO3 composites. The four different energies were tested. Based on the findings, it is possible to draw the conclusion that non-toxic, naturally occurring composites that are low in cost and have a high WO3 content could play an important part in enhancing the gamma-ray shielding capabilities of PLA/WO3 composites for low-energy radiation applications, which can used as protective cover for solar cell against harm radiation.

Radiation transmittance of the optical SiO2-based glass system

In this study, parameters related to the transmission resistance of the optical glasses described by 26.47Li2O–(20.59-x)Ta2O5–5.88ZrO2–47.06SiO2–xNb2O5 were evaluated against common ionising radiation such as gamma photons, light and heavy charged particles. A combination of FLUKA simulation code, XCOM, ESTAR, PSTAR, ASTAR, and SRIM were exploited for the evaluation of photon, electron, proton, alpha particle and carbon ion transmission data for particle energies within 15 keV–15 MeV. The increase in Nb2O5 molar concentration generally, deteriorated the photon and charged radiation shielding ability of the glasses. The present glass system showed preferred gamma radiation shielding competence compared to standard glasses and concrete shields.

Mechanical and radiation shielding properties of SWCNT reinforced polymer/glass fiber fabric‐based nanocomposite containing different filler materials: A comparative study

AbstractIn this study, polymer/glass fiber fabric‐based nanocomposite plates were fabricated with 0.01%–0.1% single‐walled carbon nanotubes (SWCNTs) and filler materials (barite, magnetite, and colemanite) using a hand layup process. Mechanical properties (e.g., tensile strength, flexural strength, and Charpy impact strength), thermal conductivity, and radiation shielding properties (e.g., gamma radiation and neutron radiation) of the specimens were determined. The results revealed that the specimens containing barite and magnetite managed to exhibit adequate mechanical properties (especially Charpy impact strength). Among different filler materials used, barite‐filled specimens outperformed colemanite and magnetite‐filled specimens in terms of mechanical properties. The mechanical performance of filler‐modified specimens can be further enhanced by adopting efficient dispersion techniques to disperse filler material and SWCNTs throughout the composite plates. The thermal conductivity of barite, magnetite, and colemanite‐filled specimens (with/without SWCNTs) increased by 30.56%–60% as compared to specimens only containing SWCNTs and neat polymer, which avoids the accumulation of heat required for radiation shielding applications. Similar to thermal conductivity, specimens containing filler materials (with and without SWCNTs) provided higher gamma and neutron radiation shielding properties as compared to neat polymer‐ and SWCNT‐modified specimens. In the case of gamma and neutron radiation shielding, barite‐ and colemanite‐filled specimens provided better results, respectively.