Removal Cross Section Research Articles

Radiation shielding for inertial electrostatic confinement fusion system utilizing concrete and water

In this investigation, the impact of water thickness and various types of concrete materials, each characterized by different densities and elemental compositions, is examined for their role in shielding a radiation generator based on Inertial Electrostatic Confinement Fusion (IECF) device. The study focuses on assessing several vital parameters, including the effective removal cross-section (∑Rt) for fast neutrons, total mass attenuation coefficients (μmt), linear attenuation coefficients (μl), half-value layer (HVL), and mean free path (MFP) for X-rays across different concrete types. Different water thicknesses around the IECF chamber, ranging from 0.5 to 10.0 cm, are investigated, and five concrete types are evaluated: Ilmenite-magnetite Concrete (IMC), Ordinary Concrete-1 (OC1), Barite-containing Concrete (BC), Ordinary Concrete-2 (OC2), and Serpentine-containing Concrete (SC). The results indicate that, among these materials, SC requires the least thickness to attenuate 2.45 MeV generated from IECF to 1/100th of its initial intensity across varying water thicknesses (6.5 cm in case of 5 cm water thickness). The values of μmt, HVL, and MFP are also calculated for different water thicknesses and X-ray energies (ranging from 0.2 to 3.0 MeV). These calculations highlight BC as the material requiring the least thickness to attenuate X-rays to 1/100th of their initial intensity. Moreover, neutron dose rate measurements are conducted on a commercial IECF system shielded with 50 cm of water and operated at a neutron intensity of 105 ns−1, which was ∼12 nSv/h on average, approximately 0.002% of the initial intensity. This underscores the efficacy of water shielding in attenuating the outcomes of IECF.

Influence of aluminum and vanadium oxides on copper borate glass: A physical/radiological study

Due to the radiation released by commonly used isotopes, many nuclear, medical, and industrial facilities require proper radiation shielding. In this work, distinct copper borate glasses intercalated with varied aluminum and vanadium oxide (Al2O3 and V2O5) content have been synthesized and used against radiation (gamma rays and fast/thermal neutrons). The different percents were as follows: [60% B2O3 + 35% CuO + (5-x)% Al2O3 + xV2O5], where x = 0, 1, and 2.5 wt.%, which was coded as BCu(5-x)Al:xV. The synthesized glass samples were characterized using Fourier transforms, infrared, and X-Raydiffraction analysis. Experimentally, the radiation shielding possessions of the samples were established using an HPGe detector at the gamma energy lines 0.356 MeV, 0.661 MeV, 1.173 MeV, and 1.332 MeV. Also, the prepared glasses were investigated theoretically using the Monte Carlo code (MCNP5) at photon energies of 0.015–15 MeV. Also, the fast and thermal neutron macroscopic effective removal cross-sections were calculated using MRCsC and JANIS-4.1 software, respectively. The prepared sample BCu2.5Al:2.5V, which has a vanadium and aluminum content of 2.5%, has the highest linear attenuation coefficient as well as the highest removal cross-section for fast, and thermal neutrons.

Evaluation the Shielding Properties of Various Water Equivalent Materials Using Different Calculation Methods and Monte Carlo

In this study, the linear attenuation coefficients (LAC), mass attenuation coefficients (MAC), half-value layer (HVL), and mean free path (MFP) of various materials such as water equivalent, ABS, Presage, RMI457, RW3, SW557, Epoxy, A150, Rhizophora spp., and Nylon-12 have been calculated using the Monte Carlo simulation method, EpiXS, Phy-X/PSD, and XCOM. Additionally, the fast neutron effective removal cross sections (ΣR) have been calculated using the empirical calculation method, Phy-X/PSD, MRCsC program, experimental and MNCP5 with the help of fast neutron mass removal cross sections. Among all the materials studied, Nylon-12 has the highest ΣR value. The calculated values of HVL, MFP, LAC, and MAC reveal that RW3, Epoxy, and Presage are the best materials in terms of their shielding properties, respectively.

Gamma-ray, fast neutron and charged particle shielding performance of 15Li2O-25BaO-(40-x)B2O3-20P2O5-xDy2O3 glass system

Gamma-ray, fast neutron and charged particle shielding characteristics of Dy3＋ activated glasses with composition 15Li2O-25BaO-(40-x)B2O3-20P2O5-xDy2O3 (x = 0, 0.2, 0.4, 0.6, 0.8, and 1.0 mol%) are analyzed in a wide incident energy for the first time. For gamma-ray shielding analysis, mass attenuation coefficient (MAC), mass energy absorption coefficient (μen), linear attenuation coefficient (LAC), mean free path (MFP), half-value layer (HVL), atomic cross-section (ACS), electronic cross-section (ECS), effective atomic number (Zeff), equivalent atomic number (Zeq), effective conductivity (Ceff), effective electron density (Neff), buildup factors (EABF and EBF), and kinetic energy released per unit mass of the absorbing material (KERMA) are calculated by using Phy-X/PSD and PAGEX softwares. For fast neutrons, fast neutron removal cross-section (FNRCS) is computed for all glass samples. For charged particle shielding analysis, mass stopping power (MSP), projected range (Rp), radiation yield (Ry), Zeff and Neff are computed using SRIM, ESTAR and PAGEX softwares. It is found that the glasses with increasing Dy3＋ have higher shielding potential. This suggests that the LBPDy1.0 sample has a potential use as shielding material for various applied fields.

Enhancing radiation shielding effectiveness: a comparative study of barium-doped tellurite glasses for gamma and neutron radiation protection

This study investigated the radiation shielding performance of the xBaO-(30-x)TeO2-35Bi2O3-35B2O3 glass system, where x = 5, 10, 15, 20 and 25, using Phy-X/PSD software and MCNPX Monte Carlo code. Key radiation shielding indicators, including attenuation coefficients, half value layer (HVL), tenth value layer (TVL), effective atomic number (Zeff), mean free path (MFP), and build-up factors, were measured within the energy range of 0.015–15 MeV. Further, the study assessed the glasses' capacity to block fast neutrons, using the fast neutron removal cross-section (ΣR) as a metric. The results showed that gamma shielding effectiveness follows the order: BaTBiB-1 < BaTBiB-2 < BaTBiB-3 < BaTBiB-4 < BaTBiB-5 at all photon energies. Additionally, the ΣR values for BaTBiB-1 to BaTBiB-5 glasses were 0.10179, 0.10263, 0.10362, 0.10581, and 0.10623 cm−1, respectively. Therefore, the findings demonstrate that including BaO enhances the gamma and neutron shielding characteristics of tellurite glasses, making them valuable for radiation-related applications.

Physical, structural and nuclear radiation shielding behavior of Ni–Cu–Zn Fe2O4 ferrite nanoparticles

In this study, Ni–Cu–Zn Fe2O4 ferrite nanoparticles have successfully been synthesized utilizing the Co-precipitation technique. The primary objectives encompassed elucidating phase purity, discerning functional groups, scrutinizing surface morphology, and conducting structural analyses. To accomplish these objectives, a battery of advanced characterization techniques was employed, including power X-ray diffraction, Transmission infrared spectroscopy, UV–Visible spectrophotometer, and Scanning electron microscopy. Furthermore, the investigation was extended to the assessment of the gamma ray shielding properties exhibited by the synthesized Ni–Cu–Zn Fe2O4 nanoparticles, spanning an energy range from 122 keV to 1330 keV. This evaluation was carried out through the utilization of a NaI(Tl) detector coupled with a PC-based multichannel analyzer. The acquired data were meticulously compared with established theoretical value. The results of this study point to a viable route for using this simple, cost-effective, and low-temperature synthesis approach to create nanomaterials suited for gamma ray shielding applications, as well as broader radiation protection. This novel technique has the potential to significantly improve radiation shielding technology. Along with this fast neutron attenuation capability of this prepared ferrite samples have been studied in terms of fast neutron removal cross section.

Radiation shielding effectiveness, structural, and mechanical properties of HDPE/B4C composites reinforced with Fe2O3-Al2O3-Al-Fe fillers

The fast neutron and gamma-ray attenuation properties of pure high-density polyethylene and its composites were investigated, including 90 HDPE/10 B4C (wt%) and 60 HDPE/10 B4C/30X (wt%) (Where X represents iron oxide, aluminum oxide, iron, and aluminum). The examined samples were analyzed using a scanning electron microscope, and their mechanical properties were assessed. The composite of 60 HDPE/10 B4C/30 α-Fe2O3 (wt%) shows better mechanical properties than those of other composites under investigation. 239Pu–Be was used as a source of fast neutrons with a neutron yield of 1.7 × 106 n s−1 and was detected by the Stilbene scintillator. Neutron removal cross-section with dependent parameters, the mean free path and half-value layer of the prepared composites, were calculated. Furthermore, the gamma-ray transmission through the produced composites has been examined. The composite containing 30% iron oxide exhibited superior shielding characteristics for neutrons and gamma rays compared to the other analyzed samples. The computed values of the shielding characteristics indicate that the produced composites are highly effective for shielding fast neutrons and gamma rays in radiation facilities.

ERCS24: An updated version of the ERCS08 program for calculations of the cross sections for atomic electron removal based on the ECPSSR theory and its variants

ERCS24: An updated version of the ERCS08 program for calculations of the cross sections for atomic electron removal based on the ECPSSR theory and its variants

An extensive benchmark analysis of advanced ceramic-concretes towards strategic material selection for nuclear applications and waste management

Ceramic concretes, with their exceptional durability and ability to incorporate a high percentage of heavy metal oxides, are of critical importance for nuclear radiation facilities, offering superior radiation attenuation characteristics essential for long-term safety and protection. This study presents a detailed evaluation of the gamma-ray shielding properties of various concrete composites, including Standard Concrete and Heavy Concretes (HC series), with densities ranging from 1.94 g/cm3 to 4.54 g/cm3. Utilizing computational methods, we analyzed several gamma-ray and neutron shielding parameters such as mass attenuation coefficients, linear attenuation coefficients, half and tenth value layers, mean free paths, exposure build-up factors, effective atomic number (Zeff), effective electron density (Neff), fast neutron effective removal cross-section (ΣR), and photon transmission factors (TFs). Our research reveals that the shielding efficacy of concrete is intrinsically linked to its density and elemental composition, with higher densities and the incorporation of heavy elements leading to enhanced attenuation capabilities. Among the concretes studied, Limonite with Steel Punch LS-a, which contains 74.53% Fe in its structure, exhibited the lowest transmission factors (TFs) across all tested thicknesses and energy levels (0.662, 1.1732, and 1.3325 MeV), indicating its superior photon attenuation potential. It can be concluded that the concrete samples with a higher Fe (iron) content in their structure demonstrate clear superiority in gamma-ray attenuation properties.

Fabrication and characterization of different PbO borate glass systems as radiation-shielding containers

Three borate glasses of 50, 35, and 15 mol% PbO-doped Ce, Sb, or Mn ions were fabricated via the melting-annealing procedure. Their structural features were inspected before and after 250 kGy of gamma irradiation using FTIR and ESR techniques. The spectra of the ESR and FTIR vibrational bands remain constant, with a minor reduction in N4 and an enhancement in density values after irradiation, indicating the large structural stability and glass compactness. Many radiation shielding parameters were studied, such as gamma dose rate (µSv/h), dose transmission %, lifetime cancer risk %, macroscopic effective removal cross-section (∑R), mass stopping power, and projected range values ​​were considered for protons particles by SRIM Monte Carlo simulation code and ESTAR program. The whole data reveals the high radiation shielding efficiency of the glasses compared to other standard shields to be used as glass immobilizers for radioactive wastes or storage containers, e.g., for nuclear medicine units in hospitals.

Evaluation of gamma and neutron radiation shielding parameters of some glass materials by Monte Carlo and theoretical method

The present study investigates the gamma-ray and neutron shielding properties of PbCu3Ti4O12, lithium borate (Li2B4O7), lithium borate glasses doped with dolomite (CaMg(CO3)) and neodymium oxide (Nd2O3) to assess their effectiveness as shielding materials against ionizing radiation. The gamma-ray shielding properties, including the attenuation and absorption characteristics of the materials were examined and compared using Geant4-based GATE simulation, XCOM, and EpiXS in the photon energy range of 80-2000 keV. When the shielding properties of the available materials were compared, it was determined that Li2B4O7-Nd2O3, PbCu3Ti4O12, Li2B4O7-CaMg(CO3), and Li2B4O7 exhibited the best shielding properties, in order from most effective to least effective. The neutron shielding properties of these materials, including scattering, absorption, and moderation capabilities, were also determined using MRCsC, Phy-X/PSD and estimation ΣR/ρ of elements. The results were then compared with the current literature. Li2B4O7, CaMg(CO3), and Nd2O3-doped lithium borate glass samples showed higher effective fast neutron removal cross-section values than water and concrete in all calculation methods. It shows that the investigated glass materials are better gamma and neutron beam absorbers and have the potential for use in gamma and neutron beam shielding applications.

Case study of Er- and Dy-doped boron-aluminosilicate glasses on radiation shielding performance in the energy range 0.015–10 MeV with MCNP6.2

The use of radiation-shielding materials has significantly increased with the advancement of new technologies. The present work aims to demonstrate that the nuclear shielding properties of boron-aluminosilicate glasses can be enhanced by doping with rare earth elements (REEs) such as erbium (Er) and dysprosium (Dy). Testing was performed by mixing different ratios of dopants into the glass system. This procedure was implemented on 13Al2O3–21B2O3-35.4SiO2-(30.6-X) Er2O3-X(Dy2O3) glass, where X = 0, 15.3, 22.1, and 30.6. MCNP6.2, SRIM, PSD, ROOT software, and XCOM databases were used as tools. MCNP6.2 software and XCOM databases were used to calculate, simulate, and validate the mass attenuation cross-sections for 15 selected gamma energies ranging from 0.01 MeV to 10 MeV. On the other hand, SRIM was used to obtain information about the mass stopping power (MSP) and stopping distance, the so-called projected range (PR), for charged particles of H+1 and He+2. Likewise, the PSD was only used to obtain a fast neutron removal cross-section (FNRCS) per density value for each element. This is referred to as the macroscopic neutron cross-section for fast neutron removal in the literature. Finally, the data analysis framework ROOT was used for calculations and graphical representations. To validate this study, the radiation-shielding properties of the material were compared with the globally accepted mass attenuation coefficient database of XCOM using MCNP6.2 simulation results. The proximity between these two is promising. The accuracy of the study was determined by examining the relative error values. The results indicate a strong correlation between the database and theoretical data. Radiation shielding properties such as mass and linear attenuation coefficients (MAC and LAC), half and tenth value layers (HVL and TVL), mean free path (MFP), effective atomic number (Zeff), effective electron density (Neff), effective conductivity (Ceff), and fast neutron removal cross-sections (FNRCS) against gamma rays suggested that the lowest X ratio indicated the highest protection. However, the MSP and PR values for the charged particles at most energies indicate the lowest protection with the lowest X ratio in the glass mixture. Finally, the glass shield with the lowest X ratio provided the highest neutron protection, similar to gamma rays. In summary, dysprosium and erbium doping in boron-aluminosilicate glasses can be tailored to specify different requirements for gamma-ray and particle attenuation, as well as neutron absorption. This study aims to fill a gap in the literature by providing a basis for future research on shielding materials based on doped boron-aluminosilicate glasses using high-atomic-number particles, such as REEs, as a radiation protection medium.

Effect of zirconium oxide nanoparticles on thermal, optical, and radiation shielding properties of Bi2O3-B2O3-MnO2 glasses

This study has explored the DSC, UV–Vis absorption spectroscopy, gamma ray and neutron shielding properties of Bi2O3-B2O3-MnO2: ZrO2 glasses. It demonstrates a unique approach to photon shielding analysis using JENDL/PD-2016 photonuclear data and employs a validated spherical neutron model for neutron shielding. Five transparent glasses were prepared with the chemical composition (in mol%) of 29Bi2O3-70B2O3-(1-x)MnO2: xZrO2, and labeled as MZ0.00 (for x = 0), MZ0.25 (for x = 0.25), MZ0.50 (for x = 0.5), MZ0.75 (for x = 0.75) and MZ1.00 (for x = 1). The glass ceramic nature of the samples has been characterized by DTA thermograms. The glass forming ability parameters (Kgl, S & H) were found to be highest for the sample MZ1.00. The UV–Visible optical absorption spectra have been interpreted, and hence the cut-off wavelength (λcut-off) and optical band gap (Eo) were evaluated. The absorption spectra have revealed the co-existence of manganese ions in three stable valence states Mn4+, Mn3+ and Mn2+ in the samples. When ZrO2 nanoparticles were added in the composition up to x = 0.50 mol%, the red shift in the cut-off wavelength (λcut-off) with gradual shrinkage in optical band gap (Eo) has been observed. Also, the linear and non-linear optical parameters viz., refractive index (no), non-linear refractive index (n2), linear optical susceptibility (χ(1)) and non-linear optical susceptibility (χ(3)) have been evaluated. These parameters showcased that B-O, Bi-O, Mn-O, Zr-O, etc. bonds could be strengthened by subsequent reduction of polarization of the trivalent ions (B3+ ions, Bi3+ ions and Mn3+ ions) in the glass system at higher concentrations of ZrO2. Photoatomic and photonuclear attenuation studies portrayed that the sample MZ0.50 has the lowest photon shielding capability. The fast neutron effective removal cross section (ΣR) was observed to be the highest for the sample MZ1.00. Thus, these glasses can be used to design the thermally stable transparent glasses, tunable optical elements, and radiation shielding materials.

Evaluation of shielding and interaction properties of different stainless steel alloys for nuclear power plant shielding

This study evaluated the gamma and neutron-shielding parameters, electron and charge particles’ interaction properties of three different stainless steel-based alloys (2507SS, 304SS and AISI1018) with densities of 7.82, 7.81 and 7.82, respectively for deployment in nuclear reactor construction. Gamma shielding parameters were evaluated with Phy-X/PSD, Py-MLBUF and GRASP computer programs within the energy range of 0.2 MeV to 15 MeV. The relative deviations (RD %) between two of these computational platforms were calculated. Fast Neutrons Effective Removal Cross-Sections (FNRCS) and Macroscopic Removal cross-section (MRCS) values for fast neutrons were calculated with Phy-X/PSD and MRCS software, while thermal/fast neutron attenuation factors were calculated with NGCals software. The continuous-slowing-down approximation (CSDA) range and total stopping power (TSP) values of H+ and He++ ions were estimated with SRIM Monte Carlo code in a wide energy range of 1–20 MeV. The projectile range of electrons was computed with ESTAR NIST software within the kinetic energy of 0.01–1000 MeV. Gamma-ray, thermal neutron and fast neutron transmission factors (TFs) values were calculated for all samples for a range of well-known energies. From the obtained results, all evaluated parameters were dependent on the composition of shielding materials, the type of radiation and the photon energy of the radiation. The maximum MAC values obtained from the three alloy samples are 0.1505 cm2/g for 2507SS, 0.1453 cm2/g for 304SS and 0.1459 cm2/g for AISI1018 at 0.02 MeV. These results projected 2507SS as a better shielding alloy when compared with other investigated alloy samples. Considering the closeness of densities of investigated alloy samples the shielding and interaction properties of all alloy samples gave excellent and similar results implying that all investigated alloys will effectively serve as a radiation-shielding material in a nuclear reactor.

EVALUATION OF NUCLEAR RADIATION SHIELDING BEHAVIOR AND STRUCTURE PROPERTIES OF NOVEL \(B_2O_3-Na_2O-K_2O-xBi_2O_3\) GLASSES

It was studied in this research the nuclear radiation shielding behavior and structure properties of the four glass samples which were composed of (80-x) B2O3-10Na2O-10K2O-xBi2O3 (x=0, 15, 30, 45 mol%) and were prepared using the melt-quenching technique. The studied samples were symbolized as Bi0.0, Bi0.15, Bi0.30, and Bi0.45 according to the Bi2O3 content values. The nuclear shielding properties have been calculated by the Phy-X/PSD program in the photon energy from 0.015 to 15 MeV. The results indicated that the values of mass attenuation coefficient (MAC) ranged from 4.2 to 88.5 cm2/g, linear attenuation coefficient (LAC) values ranged from 8.99 to 429.99 cm-1, half-value layer (HVL) values decreased from 0.077 to 0.002 cm, tenth value layer (TVL) values decreased from 1.570 to 0.020 cm, mean free path (MFP) values decreased from 0.682 to 0.009 cm, effective atomic number (Zeff) values ranged from 12.9 to 77.5, effective electron density (Neff) values ranged from 5.00 × 1023 to 8.60×1023 electrons/g, atomic and electron cross-sections (ACS and ECS) values ranged from 1.09 × 10-22 to 7.98 × 10-21 cm2/g and from 8.47 × 10-24 to 1.03 × 10-22 cm2/g respectively. The effective neutron removal cross-section (ƩR) values for prepared samples were also calculated. The results indicated that the addition of bismuth oxide leads to an improvement in the nuclear shielding properties of the prepared glass and showed that the sample Bi0.45 has the best nuclear shielding properties than concrete and commercial glasses.

Enhancing Radiation Shielding with Gadolinium(III) Oxide in Cerium(III) Fluoride‐Doped Silica Borate Glass

This study investigates the radiation shielding properties of glass samples within the xGd2O3‐5SiO2‐40Na2O‐(54.5‐x) B2O3:0.5CeF3 composition, where x varies from 0 to 10 mol.%, which is coded as GSNBCX (X = 1, 2, 3, and 4). The assessment is done through comprehensive Monte Carlo simulation and Phy‐X/PSD software analyses. The primary objective of this study is to comprehensively evaluate the radiation shielding properties of glass compositions with varying Gd2O3 concentrations. This evaluation encompasses both the attenuation of gamma radiation within the broad energy range of 0.015 MeV to 15 MeV and the assessment of fast neutron removal cross sections, with a specific focus on simulations spanning energy levels from 0.5 to 10 MeV. By examining these parameters, we aim to elucidate the impact of Gd2O3 concentration on the material’s overall effectiveness in radiation shielding applications. The results reveal a significant variation in the mass attenuation coefficient (μm) across the investigated glass samples. For instance, μm values range from 3.244 to 0.019 cm2·g−1 for GSNBC1, 20.471 to 0.025 cm2·g−1 for GSNBC2, 27.245 to 0.027 cm2·g−1 for GSNBC3, and 32.223 to 0.029 cm2·g−1 for GSNBC4. Notably, GSNBC4, characterized by a substantial Gd2O3 concentration (10 mol.%), exhibits the highest values of both μm and linear attenuation coefficient (μ). Furthermore, the investigation delves into the fast neutron removal cross section (FNRCS), which displays values of 0.97, 0.95, 0.094, and 0.93 cm−1, respectively. GSNBC1, marked by its elevated B2O3 content (54.5 mol.%), showcases the highest FNRCS. These findings underscore the efficacy of Gd2O3‐doped materials in shielding against gamma rays, holding promise for various applications in radiation protection, particularly in the medical and nuclear sectors. This study contributes valuable insights into developing effective radiation‐blocking materials for diverse industrial and scientific contexts.

On β-titanium alloys: tailoring gamma-ray, and neutron transmission properties for nuclear and biomedical applications

This study explores the gamma-ray and neutron transmission properties of β-Titanium alloys pivotal for their performance in nuclear and biomedical applications. Utilizing the Monte Carlo N-Particle (MCNP 6.3) simulations, we analyzed a spectrum of Ti-based alloys modified with elements like molybdenum (Mo), zirconium (Zr), niobium (Nb), and hafnium (Hf) to determine their radiation attenuation properties. Key parameters such as mass and linear attenuation coefficients, half-value layers, exposure buildup factors, and fast neutron effective removal cross-section values were computed, revealing significant enhancements in attenuation with the addition of high-Z elements. Specifically, alloys like Ti50Hf50 and (TiZr)40Cu60 exhibited superior photon and fast neutron attenuation due to their high-Z constituents. For instance, Ti50Hf50 showed a mass attenuation coefficient of 0.217 cm2/g and a half-value layer of 2.97 cm at 0.1 MeV photon energy, while (TiZr)40Cu60 demonstrated similar performance with a mass attenuation coefficient of 0.198 cm2/g and a half-value layer of 3.26 cm. These alloys also exhibited effective neutron removal cross-section values of 0.115 cm−1 and 0.130 cm−1, respectively. Alloys with lower-Z elements showed less attenuation, which may be beneficial in scenarios requiring reduced radiographic contrast in biomedical applications. The MCNP outcomes were in strong agreement with standard data, affirming the accuracy of computational methods in predicting material behavior. In conclusion, tailored alloy development is crucial for improving radiation shielding and diagnostic visualization, with broader implications for patient safety and treatment efficacy.

Morphology, structural, and radiation shielding characteristics of Bi2O3-B2O3-Cr2O3: ZrO2 glass ceramics

Six glass ceramics were prepared with composition (in mol %) 30Bi2O3-70B2O3 (pure sample) and (29-x) Bi2O3-70B2O3- 1Cr2O3: xZrO2 (where x = 0, 0.5, 1, 1.5, and 2) by process of melt-quenching, and subsequent two-step heat treatment method. We have studied the SEM, XRD, FTIR, and radiation shielding properties of the prepared samples. SEM micrographs and XRD spectra confirmed the formation of heterogeneous crystal phases in the samples during heat treatment. FTIR spectra revealed the presence of structural units: [BO3], [BO4], [BiO6], [ZrO6] and [CrO4−2] in the samples and their variation with the addition of ZrO2 content. EPDL2017 photoatomic and JENDL/PD-2016 photonuclear interaction databases revealed an increase in mass attenuation coefficients and a change in effective atomic numbers not exceeding 3% and 2% respectively. Mean free paths were calculated by highlighting a photonuclear absorption energy peak at ≈13.5 MeV due to the giant dipole resonance of bismuth nuclei. Fast neutron removal cross sections were determined using PHITS 3.31 spherical model simulations, which have demonstrated practical values between 0.0880 cm−1 to 0.0903 cm−1 and stability across compositions with relative differences not exceeding 3%.

Enhancing Gamma-Neutron Shielding Effectiveness of Polyvinylidene Fluoride for Potent Applications in Nuclear Industries: A Study on the Impact of Tungsten Carbide, Trioxide, and Disulfide Using EpiXS, Phy-X/PSD, and MCNP5 Code

Background: Radiation protection is crucial in various fields due to the harmful effects of radiation. Shielding is used to reduce radiation exposure, but gamma radiation poses challenges due to its high energy and penetration capabilities.Materials and Methods: This work investigates the radiation shielding properties of polyvinylidene fluoride (PVDF) samples containing different weight fraction of tungsten carbide (WC), tungsten trioxide (WO&lt;sub&gt;3&lt;/sub&gt;), and tungsten disulfide (WS&lt;sub&gt;2&lt;/sub&gt;). Parameters such as the mass attenuation coefficient (MAC), half-value layer (HVL), mean free path (MFP), effective atomic number (Z&lt;sub&gt;eff&lt;/sub&gt;), and macroscopic effective removal cross-section for fast neutrons (Σ&lt;sub&gt;R&lt;/sub&gt;) were calculated using the Phy-X/PSD software. EpiXS simulations were conducted for MAC validation.Results and Discussion: Increasing the weight fraction of the additives resulted in higher MAC values, indicating improved radiation shielding. PVDF–xWC showed the highest percentage increase in MAC values. MFP results indicated that PVDF–0.20WC has the lowest values, suggesting superior shielding properties compared to PVDF–0.20WO&lt;sub&gt;3&lt;/sub&gt; and PVDF–0.20WS&lt;sub&gt;2&lt;/sub&gt;. PVDF–0.20WC also exhibited the highest Z&lt;sub&gt;eff&lt;/sub&gt; values, while PVDF–0.20WS2 showed a slightly higher increase in Z&lt;sub&gt;eff&lt;/sub&gt; at energies of 0.662 and 1.333 MeV. PVDF–0.20WC has demonstrated the highest Σ&lt;sub&gt;R&lt;/sub&gt; value, indicating effective shielding against fast neutrons, while PVDF–0.20WS2 had the lowest Σ&lt;sub&gt;R&lt;/sub&gt; value. The Monte Carlo N-Particle Transport version 5 (MCNP5) simulations showed that PVDF–xWC attenuates gamma radiation more than pure PVDF, significantly decreasing the dose equivalent rate.Conclusion: Overall, this research provides insights into the radiation shielding properties of PVDF mixtures, with PVDF–xWC showing the most promising results.

Structural, mechanical, optical, and radiation shielding properties for borotellurite glasses

In this work, six glass samples previously fabricated were used to prepare three glass systems by the melt-quench technique. X-ray diffraction and Fourier transform infrared studied the structure of refabricated glasses. At the same time, the Makishima–Mackenzie model was used to assess the elastic moduli for refabricated glasses. The optical properties of refabricated glasses were calculated based on UV–Vis absorption. The radiation shielding features were evaluated based on the Phy-X and SRIM programs. The X-ray diffraction results exhibited the amorphous behavior for all refabricated glasses, while the Fourier transform infrared revealed several bands related to TeO2 and B2O3. The band gap values for TBBBSr, TBBBZn, and TBBBCd glasses are 3.439, 3.236, and 3.195 eV, respectively. The Young modulus values are 59.368, 57.843, and 56.358 GPa for TBBBSr, TBBBZn, and TBBBCd glasses, which indicate superior the TBBBSr glass sample on other glasses in mechanical properties. The mechanical, optical, and Fourier transform infrared results showed high compatibility. In contrast, the TBBBCd glass recorded the highest density and gamma-ray shielding properties; for example, the linear attenuation coefficient values at 15 MeV are 0.222 cm−1 for TBBBCd, 0.214 cm−1 for TBBBZn, and 0.188 cm−1 for TBBBSr. While, the TBBBZn glass showed the highest neutron shielding feature; for example, the fast neutron removal cross section is 0.088, 0.091, and 0.092 cm−1 for TBBBSr, TBBBZn, and TBBBCd, respectively. On the other hand, the TBBBSr displayed the highest shielding features for charged particles. In conclusion, the TBBBSr glass can be nominated for radiation shielding applications based on its superior mechanical properties and ability to stop charged particles.