Nuclear Attenuation Research Articles

Tailoring ZrWNb-Based Refractory High Entropy Alloys: A Multidirectional Characterization Through Elemental, Physical, Thermodynamic, and Nuclear Radiation Attenuation Properties

This study explores the development and characterization of 18 novel ZrWNb[(X)(Y)] (where XY are Hf, Ta, Mo, V, Ti) refractory high entropy alloys (RHEAs) designed to enhance mechanical robustness, thermodynamic stability, and radiation shielding effectiveness. Through a rigorous analysis, we evaluated the elastic modulus, entropy, and enthalpy of mixing, atomic size difference, valence electron concentration, and the omega parameter to understand the alloys’ phase behavior and structural integrity. Our findings revealed a broad range of elastic modulus values, indicating diverse mechanical adaptability suitable for high-stress applications. The thermodynamic assessment highlighted several RHEAs with favorable phase stability, particularly ZrWNbTaHf and ZrWNbTiTaHf, which are poised for high-performance usage due to their balanced mixing entropy and enthalpy. This study also benchmarks the RHEAs against conventional alloys, with sample R1 exhibiting the lowest fast neutron effective removal cross section, underscoring its superior neutron shielding capabilities. Additionally, R1 demonstrated exceptional photon attenuation, as evidenced by its competitive half-value layer performance across an extensive energy spectrum. Collectively, these results position R1 as a standout candidate, offering a significant advancement in materials science for applications demanding stringent radiation shielding, such as in nuclear reactor environments and space exploration.

An experimental study on the nuclear radiation attenuation properties of Fe–Sb–Pb doped concretes prepared with different cement types

An experimental study on the nuclear radiation attenuation properties of Fe–Sb–Pb doped concretes prepared with different cement types

BaO-doped Na2O–CaO–P2O5 bioactive glasses: A closer look at radiation attenuation properties for medical applications

This study investigates the nuclear radiation attenuation characteristics of bioactive glasses with the system (26-x)Na2O-xBaO-29CaO–45P2O5, where x represents the molar percentage of BaO (0, 5, 10, 15). For this purpose, several parameters of shielding gamma radiation, such as the mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), effective atomic number (Zeff), effective electron density (Neff), atomic cross-section (ACS), electronic cross-section (ECS), equivalent atomic number (Zeq), and transmission factor (TF) were calculated. The calculations were performed across different photon energy ranges (0.015–15 MeV) using Phy-X/PSD software and validated using the WinXCOM program. The results obtained from both the software platforms exhibited a high degree of agreement. Among the investigated glasses, the BNCP-15 glass, which had the highest BaO concentration, demonstrated the highest values for MAC, LAC, Zeff, Neff, ACS, ECS, and Zeq, while displaying the minimum values for HVL, TVL, MFP, and TF. For example, the LAC values at 15 MeV were found to be 0.056, 0.063, 0.070, and 0.077/cm for BNCP-0, BNCP-5, BNCP-10, and BNCP-15, respectively. Consequently, the BNCP-15 glass exhibited superior radiation attenuation performance in comparison to the other BNCP glasses examined in this study.

Exploring critical behavioral differences in physical, structural, and nuclear radiation attenuation properties of produced High Entropy Alloy (HEA) and Refractory-High Entropy Alloy (RHEA) samples

Refractory-High entropy alloys (RHEAs) are known for their exceptional mechanical and radiation-resistant properties, making them promising materials for use in nuclear reactors. Their high entropy composition, which consists of multiple elements in roughly equal proportions, can create a stable microstructure that withstands high levels of radiation damage. The objective of this work is to further our comprehension of the unique behavioral, physical, structural, and nuclear radiation attenuation characteristics shown by High-Entropy Alloys (HEA) and Refractory-High entropy alloy (RHEA) materials. Accordingly, two high entropy alloy (HEA) samples through two different compositions were produced. The first composition under consideration is the typical high-entropy alloy (HEA) defined as MnCrFeNiCoMo0.5. The second composition under consideration is a refractory high entropy alloy (RHEA) characterized by the following elemental composition: TiZrNbHfVTa0.1. SEM and EDX analyses were conducted in terms of determining their physical and structural attributes. Next, a133Ba radioisotope together with a HPGe detector were utilized for gamma-ray transmission experiments. Finally, a241Am/Be source and a gas proportional detector were used for neutron absorption experiments for HEA and RHEA samples. The alloy structures displayed a unique degree of uniformity. Throughout the RHEA phase, the incorporation of refractory elements did not provide any discernible adverse impacts on the physical stability. The counting spectrum provided a clear explanation of the gamma ray absorption features shown by the RHEA (R) sample, highlighting its exceptional absorption properties. Regarding the absorption properties of neutrons, it was observed that RHEA had a comparatively reduced amount of absorption. Therefore, it can be concluded that the basic structure of RHEA grants it superior gamma-ray attenuation qualities compared to HEA. It can be concluded that RHEA demonstrates superior applicability as a material in comparison to HEA, especially in situations involving the use of fuel rods, where maintaining of neutron quantity has paramount importance for achieving optimum neutron activation.

Potential application of foveal structural measurements in treatment decision for retinopathy of prematurity: an OCT-based study

PurposeTo investigate foveal changes in infants with ROP not requiring treatment(nROP) and ROP infants needing treatment (tROP) using a handheld SD-OCT device.MethodWe performed horizontal SD-OCT scans through the fovea in 156 eyes of 81 infants diagnosed with ROP. Foveal immaturity indices including the presence of inner retinal layers (IRL), absence of foveal outer nuclear layers widening (ONL) and attenuation of hyperreflective outer segment layers (OS), presence and type of cystoid macular edema (CME), epiretinal membrane (ERM), foveal pit depth (FPD), foveal pit width (FPW) and central foveal thickness (CFT) were calculated. The multivariate logistic regression model was used to predict the need for treatment based on OCT measurements.ResultsThe shape of the foveolar pit was not significantly different among tROP and nROP groups (P-value = 0.287, Chi-square test). IRL extrusion was incomplete in both tROP and nROP groups (P-value = 0.0.41, Chi-square test). Nevertheless, the presence of thicker IRL was more frequent in the nROP group in comparison with the tROP group (100% vs.64.8%, P-value = 0.001). CME was observed in 29% of eyes in the tROP group and 40% of eyes in the nROP group; however, this difference was not statistically significant (P-value = 0.32, Chi-square test). ERM was detected in 15 (75%) and 84 (65.6%) eyes in the nROP and tROP groups, respectively (P-value = 0.39, Chi-square test). Multivariate logistic regression analyses showed that the need for treatment was significantly associated with gestational age (GA), CFT and FPD (P-values 0.001 and 0.002 respectively).ConclusionsThis study demonstrated GA, foveal pit depth and the central foveal thickness could accurately predict the need for treatment with sensitivity, specificity, and diagnostic accuracy of 97%, 65% and 91.7% respectively.

Nuclear attenuation ability of ternary alumina-borate glass system for medical shielding applications

The present study aims to delve into sodium alumina-borate glass systems doped with transition metals by means of their optical properties and gamma attenuation performance, with a specific focus on their nuclear shielding applications. By leveraging advanced computational tools and simulation techniques, such as FLUKA and XCOM software, this research endeavours to investigate the optical properties and the gamma/radiation shielding ability of the glass system involved. The study seeks to elucidate the fundamental mechanisms governing optical transmission, radiation attenuation, and the overall shielding efficacy of these innovative glass systems. The results show that the optical properties as well as nuclear shielding ability of the glass system, including optical transmission, absorption coefficient, and half value layer (HVL), are significantly affected by Fe2O3 concentrations. Therefore, the incorporation of transition metals leads to enhance the attenuation of gamma rays, indicating an increase in the material's shielding efficiency against incident radiation. The findings of this study have important implications for the design and development of glass materials for various applications, such as nuclear energy, radiation detection, and optical communication.

Nuclear radiation attenuation and physicomechanical features for yttrium aluminum garnet/cerium zirconate composites

Nuclear radiation attenuation and physicomechanical features for yttrium aluminum garnet/cerium zirconate composites

Study of mechanical, thermal, and nuclear radiation attenuation properties of tourmaline loaded heavy weight heat resistant concrete as reactor shielding materials

Three heavy weight concrete mixtures incorporating barite and goethite as coarse and fine aggregates, respectively, were prepared in order to examine the nuclear radiation attenuation properties of such concrete. The three mixtures incorporated 0 wt%, 25 wt%, and 50 wt% tourmaline ore by mass as partial replacement of fine aggregates (goethite). Workability in terms of slump test and mechanical properties in terms of compressive and tensile strength tests were carried out. Moreover, physical properties in terms of bulk density and water absorption and porosity tests were done. Finally, thermal analysis and nuclear radiation attenuation measurements were performed. Ten different gamma-ray energy lines up to 1407 keV were used to determine the mass attenuation coefficients (σ) of gamma rays for the concrete specimens. Good agreement was obtained between the experimental results and theoretical calculations carried out using “WinXCom” computer program. Four neutron energy bands (slow neutrons, total slow neutrons, neutrons of energies greater than 0.4 eV as well as neutrons of energies greater than 10 keV) were used to determine the macroscopic neutron cross-sections (Σ) for the concrete mixtures under investigation. Additionally, once the optimum results of mixing proportions were achieved, the study was expanded to examine the effect of heat on the mechanical and nuclear properties of such concretes. Results showed that the addition of tourmaline ore to the concrete mixtures has significantly improved its mechanical properties, in addition to the obvious improvement in its ability to attenuate neutrons of different energy bands. Heating of concrete specimens up to 400 °C show no significant effect on the attenuation of gamma rays, while a slight decrease in the ability of samples to attenuate neutrons. Finally, concrete mix containing 50 wt% tourmaline is recommended as a heat resistant concrete at 100 °C and 400 °C, for power nuclear reactors.

Towards obtaining the optimum physical, optical and nuclear radiation attenuation behaviours of tellurite–germanate glasses through Eu2O3 reinforcement: Glass synthesis, experimental and theoretical characterisation study

We report the physical, optical and nuclear radiation attenuation behaviours of tellurite–germanate (TeO2–GeO2–PbO) glasses reinforced with varying amounts of Eu2O3. The samples were synthesised using the conventional melt-quenching method and had the following composition (in wt.%): 33.34TeO2 - 33.33GeO2 - 33.33PbO (TGP). Different concentrations of Eu2O3 (in wt.%) were added to the glass composition, labelled TGP1, TGP2 and TGP3. The physical, optical and nuclear radiation attenuation properties were measured using both experimental and theoretical methods. At room temperature, the visible to near-infrared optical absorption spectrum ranged from 400 to 900 nm. The TGP1 sample with 1 wt% The Eu2O3 additive exhibited the lowest absorbance and the highest transparency. The TGP1 sample also exhibited the highest nuclear radiation absorption properties. The gamma-ray absorption capabilities of TGP1 were demonstrably superior to those of various types of glass shields and other old- and new-generation concrete-shielding materials. Thus, adding 1 wt% Eu2O3 to tellurite–germanate glasses would ‘improve nuclear radiation absorption and optical properties. It can also be concluded that expanded scientific community investigations in this area would be a significant step toward gaining a deeper understanding of these glass structures and determining what other optimisation tasks the addition of 1 wt% Eu2O3 can accomplish.

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.

Alteration in the optical, structural, and nuclear radiation attenuation characteristics of polyvinyl alcohol/lead oxide (PVA/PbO) films

Alteration in the optical, structural, and nuclear radiation attenuation characteristics of polyvinyl alcohol/lead oxide (PVA/PbO) films

Elucidating the influences of Tantalum (V) oxide in Bi2O3–TeO2–ZnO ternary glasses: An experimental characterization study on optical and nuclear radiation transmission properties of high-densityglasses

We report the optical and experimental gamma-ray and neutron attenuation properties of tantalum pentoxide reinforced Bi2O3–TeO2–ZnO ternary glasses with a nominal composition of 10Bi2O3–70TeO2-(20-x)ZnO-xTa2O5 (where x = 0,2,4, and 6 mol%). Measurements of transmittance and absorbance spectra for all of the synthesized samples are performed with Analytik Jena Specord 210 plus device between the range of 190–1100 nm. Moreover, 133Ba and 241Am/Be sources are utilized for experimental gamma-ray and neutron attenuation studies of BTZT glasses. According to results, the absorption edge is consistently moved from 380 nm to 390 nm as a result of ZnO/Ta2O5 translocation. In addition to decrease in optical band gap values of glass series, the fact that doping the structure containing Ta2O5 is lead to an increase in Urbach energies. The obtained irregularity through an increasing Ta2O5 additive is also changed the overall nuclear radiation attenuation properties of the BTZT glasses. The gamma-ray attenuation properties are obviously enhanced within the energy range of 133Ba radioisotope. The attenuation properties against fast neutron emitted from 241Am/Be were significantly enhanced through increasing Ta2O5 contribution. It can be concluded that BTZT6 glass sample may be regarded as a beneficial glass composition for multifunctional applications. It can be also concluded that ZnO/Ta2O5 translocation in Bi2O3–TeO2–ZnO ternary glasses may be regarded as a monotonic tool where the neutron attenuation properties should be strengthened in addition to gamma attenuation properties.

Bismuth(III) oxide and boron(III) oxide substitution in bismuth-boro-zinc glasses: A focusing in nuclear radiation shielding properties

Doping the glass structure with Bi2O3 `is known to increase structural stability, and to drastically alter physical parameters including density and molar volume. The goal of this work was to assess the nuclear radiation attenuation competences of several types of glasses based on the xBi2O3-(70-x)B2O3-8BaO-16ZnO-5.5SiO2- 0.5Sb2O3 system. In order to determine the requisite gamma shielding parameters, as well as effective conductivity at 300 K and buildup factors, five different glasses with varied Bi2O3 concentration (i.e., from 10 mol.% to 30 mol.%) were examined thoroughly. These critical parameters were determined using the Phy-X/PSD program. In addition, factors such as half value layer (HVL), tenth value layer (TVL), and mean free path (mfp) were examined over a wide energy range of 0.015–15 MeV. The findings revealed that the amount of Bi2O3 reinforced in each sample is critical in determining the samples' shielding abilities. The linear attenuation coefficients (µ) and mass attenuation coefficient (µm) values were reported in the highest level for the sample with the highest Bi2O3 content. For glass sample A5, the lowest mean free path, half value layer, and tenth value layer values were also reported. The effective conductivity and effective atomic number had an inverse relationship with photon energy, meaning that as energy increased, the effective conductivity and effective atomic number declined fast, especially in low-energy regions. The greatest values for both parameters were found in glass sample A5. Furthermore, the exposure buildup factor and energy absorption buildup factor values for glass sample A5 were the lowest. A5 glass sample with the chemical composition 30Bi2O3-(70−30) B2O3-8BaO-16ZnO-5.5SiO2- 0.5Sb2O3 and a density of 5.8391 g/cm3 was found to have exceptional gamma-ray attenuation qualities, according to our findings. It can be concluded that the prospective attributes of Bi2O3-doped glass systems and associated glass compositions would be beneficial for scientific community in terms of providing a clearer view for some advanced applications of these glass types.

Synergistic effect of boron nitride and graphene nanosheets on behavioural attitudes of polyester matrix: Synthesis, experimental and Monte Carlo simulation studies

We report the synergistic effects of boron nitride and graphene nanosheets on physical, structural, and nuclear radiation attenuation properties of polyester matrix-incorporated nanocomposites. Some critical material properties are thoroughly evaluated for several types of synthesized samples. Polyester is employed to strengthen graphene and boron nitride nanolayers, and their characteristics are investigated in detail. Additionally, we report the gamma-ray and fast neutron attenuation characteristics of synthesized nanocomposites to get a better understanding of the reinforcing effect as a function of material type and weight percentage. Thermal analysis findings indicate that adding graphene lowers the decomposition temperature but co-adding graphene and BNNS enhances thermal decomposition in comparison to graphene itself. Tensile tests showed that the inclusion of both GRP and GRP/BNNS strengthens the material. Among the polyester composite samples analyzed, the G3 sample with the most GNP reinforcement had the lowest HVL values throughout the broadest range of energy levels investigated. The recent findings may be beneficial to the scientific community in terms of incorporating these reinforcing types and ratios into polyester materials for a variety of applications, including industrial and research purposes.

Ubiquitin-specific protease 1 inhibition sensitizes hepatocellular carcinoma cells to doxorubicin by ubiquitinated proliferating cell nuclear antigen-mediated attenuation of stemness.

Currently, resistance to the chemotherapeutic agent doxorubicin (Dox) in hepatocellular carcinoma (HCC) cells is an obstacle in developing effective Dox-targeted clinical therapies. Ubiquitin-specific protease 1 (USP1) plays a crucial role in the progression of multiple cancers. In this study, the purpose was to investigate the effect of USP1 depletion with chemotherapeutant Dox on the HCC cells. Flow cytometry was used to detect the ratio of apoptosis. The expression levels of selected proteins were evaluated by western blotting. In addition, the expression of genes was quantitated by quantitative real-time PCR assay. Coimmunoprecipitation was performed to confirm the interaction between USP1 and proliferating cell nuclear antigen (PCNA). Sphere formation assay was carried out to investigate the cancer stemness. Subcutaneous xenograft and orthotopic liver tumor models were established to examine the growth of tumor. Knockdown of USP1 increased the rate of Dox-induced apoptosis in stem-like and nonstem-like HCC cells. The combination of Dox and the USP1 inhibitor SJB3-019A (SJB3) markedly enhanced apoptosis in the primary liver carcinoma/PRF/5 and MHCC-97H cell lines. Notably, Dox/SJB3-induced tumor inhibition was further determined in vivo using a xenograft and orthotopic liver tumor model. Mechanically, USP1 inhibition via SJB3 or short hairpin RNA significantly decreased cancer stemness, including sphere formation ability and the expression of Nanog, Sox2, and c-Myc. The sensitization of HCC to Dox by SJB3 is attributed to the upregulation of PCNA ubiquitylation. Thus, genetic or pharmacological inhibition of USP1 restored the sensitivity of HCC cells to Dox in vitro and in vivo , representing a new potential therapeutic strategy for HCC.

Gamma, neutron, and heavy charged ion shielding properties of Er3+-doped and Sm3+-doped zinc borate glasses

AbstractThis study aimed to investigate the nuclear radiation shielding properties of erbium (Er)-reinforced and samarium (Sm)-reinforced borate glasses. In the 0.015–15 MeV photon energy range, attenuation coefficients, as well as half-value layer tenth-value layers, and the mean-free path have been calculated. Additionally, effective, and equivalent atomic numbers, effective atomic weight, electron density, and exposure and energy absorption build-up factors were also calculated. To evaluate the overall nuclear radiation attenuation competencies of Er-rich and Sm-rich glasses, effective removal cross-section values for fast neutrons and projected range/mass stopping power values for alpha and proton particles were also determined. The glass sample BZBEr2.0 had the highest linear and mass attenuation coefficients (µandµm), effective conductivity (Ceff), the effective number of electrons (Neff), and effective atomic number (Zeff) values as well as the lowest half-value layer (T1/2), tenth value layers (T1/10), mean free path (λ), exposure build-up factor, and energy absorption build-up factor values.µmvalues were reported as 2.337, 2.556, 2.770, 2.976, 2.108, 2.266, 2.421, 2.569, and 2.714 for BZBEr0.5, BZBEr1.0, BZBEr1.5, BZBEr2.0, BZBSm0.0, BZBSm0.5, BZBSm1.0, BZBSm1.5, and BZBSm2.0 glass samples at 0.06 MeV, respectively. The results showed that Er has a greater effect than Sm regarding the gamma-ray shielding properties of borate glasses. The results of this investigation could be used in further investigations and added to older investigations with the same aim, to aid the scientific community in determining the most appropriate rare-earth additive, to provide adequate shielding properties based on the requirement.

Study of Mechanical, Thermal, and Nuclear Radiation Attenuation Properties of Tourmaline Loaded Heavy Weight Heat Resistant Concrete as Reactor Shielding Materials

Study of Mechanical, Thermal, and Nuclear Radiation Attenuation Properties of Tourmaline Loaded Heavy Weight Heat Resistant Concrete as Reactor Shielding Materials

Fabrication, physical, linear optical, and nuclear radiation attenuation features of sodium borosilicate glasses

Fabrication, physical, linear optical, and nuclear radiation attenuation features of sodium borosilicate glasses

The influence of heating on mechanical and nuclear properties of reactive powder concrete as a protective shield in nuclear facilities

Based on determining the optimum concrete shielding in terms of its nuclear and mechanical properties, the difference between the performance of ordinary concrete (O.C.) and a new generation of reactive powder concrete (RPC) incorporating different contents of steel fibers (0, 1, 2, and 3 wt % of cement) were studied. Density, compressive and tensile strengths, x-ray diffraction (XRD), scanning electron microscope (SEM), and differential thermal analysis (DTA) were used to examine the characteristics of the investigated samples. Nine different gamma-ray energy lines up to 1407 keV were used to determine the mass attenuation coefficients (σ, cm2/g) of gamma rays for the concrete samples. Three types of neutron energies (slow neutron, total slow neutron, and neutron with energy greater than 10 keV) were used to determine the macroscopic neutron cross-sections (Σ, cm−1) for the prepared concretes. The study was extended to conduct at different five temperatures (25, 100, 350, 500, and 700 °C) as simulations for nuclear reactors in the cases of operation and accidents. The results showed that content of steel fiber somewhat has a positive effect on the mechanical and nuclear properties of RPC. Furthermore, the outcomes illustrated that at room temperature, the RPC gave a superiority in mechanical properties and nuclear attenuation properties for gamma radiation but for neutrons the preference was for the ordinary concrete. After exposure of both types of concrete to high temperatures, the nuclear and mechanical properties of the RPC have improved in contrast to what happened to the ordinary concrete.

The impact of Co addition on neutron-photon protection characteristics of red and yellow clays-based bricks: An experimental study

High strength and heat resistance properties of radiation shielding materials are among the most sought properties. Due to their mechanical and thermal properties, bricks can be a good alternative for radiation protection applications. In this respect, nuclear radiation attenuation parameters of seven brick samples containing different amounts of Cobalt metal (0, 5, 10, 20, 30, 40, 50 %wt) were examined in this study. Initially, SEM-EDX analysis of bricks were carried out to determine the elemental composition and structure of the bricks. Next, the bricks were exposed to gamma rays with 53.16, 79.61, 80.99, 276.39, 302.85, 356.01, 383.84 keV photon energies emitted from Barium-133 radioactive source and the transmitted photon intensities were detected by utilizing Ultra-Ge detector. Mass attenuation coefficient (MAC), effective atomic number (Zeff), Half Value Layer (HVL), Mean Free Path (MFP) and exposure buildup factors (EBF) values of bricks were determined by experimentally and EpiXS program. At 53.-383 MeV photon energy interval, it is found that the MAC values for S0–S6 brick samples range between 0.427 and 0.097 cm2/g and 1.130–0.0961 cm2/g. In addition, the neutron shielding features of the bricks under study were assessed by calculating effective removal cross section (ΣR). It is noticed that the ΣR values of the samples gradually grow from 0.057 cm−1 to 0.1392 cm−1 with increasing Co addition. It has been concluded that rising the Co addition improves the gamma and neutron shielding capacity of the brick samples.