Exposure Buildup Factors Research Articles

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

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

Experimental and theoretical investigation on physical, structure and protection features of TeO2–B2O3 glass doped with PbO in terms of gamma, neutron, proton and alpha particles

Glass series of composition 70TeO2- (30-x)B2O3- xPbO (where x = 2, 6, 10, 14 and 20 mol%) is prepared using melt-quenching technique. The glass structure was investigated by X-ray diffraction (XRD). Manufactured glass density, molar volume and Fourier transform infrared spectroscopy (FTIR) were measured. Shielding parameters against gamma-rays including, linear attenuation coefficient (μ), mass attenuation coefficients (μm), half-value layer (HVL) and mean free path (λ) were measured experimentally at energies of 0.664, 1.177 and 1.334 MeV using Cs137 and Co60 point sources and NaI(TL) scintillation detector. The measured parameters were compared with those calculated using XCOM program with a good agreement between them. To fully comprehend the shielding efficiency of the prepared glasses, several shielding parameters including, μm, HVL, effective atomic number (Zeff), electron density (Nel), equivalent atomic number (Zeq), exposure and energy absorption buildup factors (EBF & EABF), radiation protection efficiency (RPE) and kerma relative to air (Ka), were evaluated in the photon energy range 0.015–15 MeV and compared with some materials that commonly used as gamma-ray shielding. The findings demonstrate the viability of employing the current glass composition as an effective agent for gamma-ray shielding and fully protection (100%) for x-ray. The macroscopic effective removal cross section (ΣR) of the prepared glasses were calculated and compared with those of frequently used neutron shielding materials. Finally, the mass stopping power (MSP) and projected range (PR) values of proton (H1) and alpha particles (He+2) have been evaluated in the energy range 0.01–15 MeV. The results show that, increasing PbO content improves shielding characteristics. Among the examined samples, the S5 glass sample was found to be superior in terms of photon, neutron, proton and alpha particles protection. These results indicate that, the prepared glass samples are highly appropriate nuclear shielding material that can be used in many applications.

Computation of Gamma Buildup Factors and Heavy Ions Penetrating Depths in Clay Composite Materials Using Phy-X/PSD, EXABCal and SRIM Codes

Most investigations of the gamma-shielding abilities of materials are often based on the Beer-Lambert law including recent studies on clay-polyethylene composites. The findings are usually silent on the secondary radiation effects that commonly occur due to photon buildup, known as Energy Absorption Buildup Factor (EABF) and Exposure Buildup Factor (EBF). In this work, the computation of EABF and EBF in the region of energy 0.015–15 MeV at different penetration depths or mean free paths up to 40 mfp—and simulation of 100 keV of Cs and Sr ion-penetration profiles of clay–polyethylene composites (A–G) containing 0–30 wt% low density polyethylene (LPDE)—was carried out. The buildup factors computation was performed using Phy-X/PSD and EXABCal codes, and the ion-penetrating profile was studied using a Monte Carlo simulation code called Stopping and Range of Ions in Matter (SRIM). The EABF and EBF values are functions of the photon energy and the penetration depth. In the region of intermediate energy, the EABF and EBF values are higher for each of the samples. For a given mfp, the peak value of either EBF or EABF of each sample increases with LDPE wt% in the clay matrix. The projected range of both Cs and Sr ions in the samples decreased with increasing sample bulk densities, with Cs having a higher projected range than Sr in all the samples. The Cs and Sr ions have the lowest respective projected ranges in sample A (of bulk density 2.03 g·cm−3; 0 wt% of LDPE), while the highest projected ranges were recorded in sample G (of bulk density 1.34 g·cm−3; with 30 wt% of LDPE), respectively. This study reaffirmed the suitability of clay composite for gamma-ray shielding applications; however, it may not yet be ready to be used as a backfill material to mitigate the migration of fission products present in radioactive nuclear wastes.

Comparison of Monte Carlo simulations and theoretical calculations of nuclear shielding characteristics of various borate glasses including Bi, V, Fe, and Cd

The aim of this study is to evaluate both buildup factors and photon attenuation effectiveness of some borate glasses doped by Cd, Fe, V, and Bi. The mass attenuation coefficients (μm) of these glass systems have been calculated via MCNP6 and GEANT4 computer simulation codes over 0.02–10 MeV energy range and compared with the theoretical results of WinXCOM program. And then, half-value layer, (HVL), mean free path (MFP), and effective atomic number (Zeff) for the different content based glasses have been determined. Through G-P fitting process, exposure buildup factors (EBF) have been found in the energy range of 0.015–15 MeV up to 40 mfp. It can be concluded that SrBiO20 glass is alternative material in terms of photon attenuation, respectively.

Calculation of gamma-ray buildup factors for some medical materials

In recent years, novel materials with protective qualities against ionizing radiation have been discovered. Important concepts include the continued use of X-rays for diagnosis and treatment, particularly in the radiological energy range, as well as the calculation of the radiation attenuation properties of such materials, the buildup factor and the attenuation coefficients. Radiation shielding is characterized by parameters such as the linear attenuation coefficient (cm−1), equivalent atomic number (Zeq), exposure buildup factor (EBF) and exposure absorption buildup factor (EABF). Radiation is often employed in the diagnosis and treatment of cancer and accurate calculation of the absorbed dosage during radiation treatment, which is one of the most popular cancer treatments. It relies on accurate modeling of the radiation beams administered to the patient and their interaction with the environment in which they are absorbed. In this research, the shielding characteristics of water, fat and bone related to human tissue are investigated. Using the Phy-X/PSD software, the equivalent atomic number (Zeq), EBF and EABF were determined.

Gamma-ray-shielding parameters of carbon–aramid epoxy composites

Radiation has been one of the most important phenomena since its discovery, and it has been used in different fields. Due to its hazardous effects, it should be shielded, and thus, new alternative materials should be developed. In this study, the radiological parameters of two types of composite materials were calculated at gamma ray energies of 10−3–105 MeV. These gamma-ray-shielding parameters are the mass attenuation coefficient, linear attenuation coefficient, mean free path, half-value layer, tenth-value layer, atomic cross-section, electronic cross-section, effective atomic number (Zeff), effective electron density (Neff), effective conductivity (Ceff), equivalent atomic number (Zeq) and exposure buildup factor of the two different composites. The calculations were done using the Phy-X/PSD software.

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

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

A Comparative Study on the Radiation Attenuation Properties of Iron and Stony Meteorites: A Case of Mundrabilla and NWA 7629 Meteorites

The goal of this paper is to compare and investigate the radiation attenuation properties of Mundrabilla and NWA 7629 meteorites in terms of the photon, fast neutron and charged particles. The linear attenuation coefficients of Mundrabilla are higher than those of NWA 7629. The half value layers, tenth value layers and mean free paths of NWA 7629 are greater than those of Mundrabilla. The effective atomic number, effective electron density, equivalent atomic number and effective conductivity of the Mundrabilla are nearly constant between 0.015 MeV–15 MeV. Both the exposure build-up factors and energy absorption build-up factors are maximum at 0.8 MeV for Mundrabilla and NWA 7629. The projected/ continuous-slowing-down approximation (CSDA) ranges for charged particles for NWA 7629 are higher than those of Mundrabilla. The fast neutron attenuation of Mundrabilla is better than those of NWA 7629. Consequently, it can be concluded that photon, fast neutron and charged particles attenuation capability of Mundrabilla are better than NWA 7629 due to the nickel content, higher density and higher content of iron.

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

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

Numerical Investigation on Photon Sensing Parameters for Some Thermoluminescence Dosimeters: A Comparative Study

In the present work, twelve inorganic thermoluminescence dosimeteric (TLD) materials doped with some rare earth elements (LiF:Sm, LiBaP2O7:Eu, CaCO3:Eu, CaSO4:Dy, SrSO4:Sm, CdSO4:Dy, BaSO4:Eu, Li2B4O7:Dy, MgB4O7:Gd, Al2O3:Gd, MgAl2O4:Ce and LiCaAlF6:Eu) and three organic TLD materials (C3H7NO2, C7H8O2 and C4H6BaO4) were selected for comparative analysis on the basis of different photon sensing parameters. About nine photon sensing parameters viz. mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), mean free path (mfp), half value layer (HVL), tenth value layer (TVL), effective atomic number (EAN), effective electron number (EEN), exposure buildup factor (EBF) and energy absorption buildup factor (EABF) were obtained for the selected fifteen TLDs. The simultaneous variation of these photon sensing parameters for the selected TLDs with photon energy and composition has been analyzed. The results of present comparative analysis help radiation physicists to easily select a particular dosimeter for their research laboratory from different existing compositions. All photon sensing parameters viz. MAC, LAC, mfp, HVL, TVL, EAN, EEN, EBF and EABF for selected TLDs strongly depend upon incident energy and chemical composition in lower and higher energy regions. Among the selected TLDs; BaSO4: Eu3+ offers best results (maximum values for MAC, EAN, EEN; and minimum values for mfp, HVL, TVL, EBF, EABF); whereas MgB4O7:Gd3+ offers EAN value close to tissue and less variation in most of the sensing parameters with respect to photon energy.

A Comparative Study on the Radiation Attenuation Properties of Iron and Stony Meteorites: A Case of Mundrabilla and NWA 7629 Meteorites

The goal of this paper is to compare and investigate the radiation attenuation properties of Mundrabilla and NWA 7629 meteorites in terms of the photon, fast neutron and charged particles. The linear attenuation coefficients of Mundrabilla are higher than those of NWA 7629. The half value layers, tenth value layers and mean free paths of NWA 7629 are greater than those of Mundrabilla. The effective atomic number, effective electron density, equivalent atomic number and effective conductivity of the Mundrabilla are nearly constant between 0.015 MeV–15 MeV. Both the exposure build-up factors and energy absorption build-up factors are maximum at 0.8 MeV for Mundrabilla and NWA 7629. The projected/ continuous-slowing-down approximation (CSDA) ranges for charged particles for NWA 7629 are higher than those of Mundrabilla. The fast neutron attenuation of Mundrabilla is better than those of NWA 7629. Consequently, it can be concluded that photon, fast neutron and charged particles attenuation capability of Mundrabilla are better than NWA 7629 due to the nickel content, higher density and higher content of iron.

Comprehensive evaluation on gamma radiation resistance of chromium (III) ions incorporated bismuth fluoro-lead-borate glasses

Gamma-ray shielding properties of high dense glassy system (bismuth fluoro-lead-borate doped with chromium (III) ions) with composition of (25-x)PbF2–25Bi2O3–49.8B2O3–0.2Cr2O3- xCaF2- (where x = 0 (S1), 5 (S2), 10 (S3), 15 (S4), 20 (S5), and 25 (S6) mol%) have been investigated. Phy-X/PSD software was used to achieve this purpose in photon energy range (0.15–15 MeV). Additionally, the superior glass shield sample was compared to several types of glass and concrete shields. Results revealed that each photon energy value investigated the maximum linear attenuation coefficient (µm) values for the S1 glass sample with the heaviest element contribution in its structure were detected at the maximum level. In terms of the µm, there was a difference of roughly 0.5 cm2/g in the S1 and S6 glasses. The S1 sample with the highest µm also had the lowest T0.5 and mean free path (λ). The heavy element contribution to the S1 sample was reflected in the effective atomic number values, which provided the S1 sample with the highest Zeff values. Values of exposure and energy absorption buildup factors (EBF and EABF) were confirmed that the sample S1 has the minimum values. Our findings showed that S1 sample may be considered as superior gamma-ray shielding properties among all studied glasses.

Gamma-ray shielding, electrical, and magnetic properties of α-Fe2O3/Al/HDPE nanocomposites

In this work, different ratios of iron oxide (α-Fe2O3) and aluminum metal (Al) nanoparticles in powder shape have been used to prepare HDPE nanocomposites for γ-rays shielding applications. The electrical and magnetic properties of prepared samples were investigated. The WinXCom and MCNP5 programs have been used to calculate the mass attenuation coefficients (μ ρ −1) of γ-rays for the prepared samples. The μ ρ −1 for the prepared samples have been measured experimentally via a narrow beam of γ-rays at energies of 662, 1173, and 1332 keV from 131Cs and 60Co radioactive sources. The impact of α-Fe2O3 and Al on the γ-ray shielding ability of prepared composites have been clarified. The exposure buildup factor (EBF) has been calculated at energies of 0.015, 0.1, 1, and 10 MeV using MCNP5 program. The results indicated that the fillers affected the EBF at photon energies less than 0.1 MeV. HDPE as a polymeric matrix shows very stability with non-polar features against temperature and frequency. However, the prepared nanocomposites show a remarkable enhancement of their dielectric and electrical properties. Furthermore, the magnetic measurements depict unsaturated weak ferromagnetic behavior for α-Fe2O3 nanocomposites, and diamagnetic characteristics for HDPE and Al. The HDPE-based nanocomposites showed improved electrical and magnetic properties along with improved ability to attenuate low-energy γ-rays compared to pure HDPE.

Evaluation of photon interaction parameters of Anti-HIV drugs

Medical treatment inevitably exposes individuals to radiation, including those taking drugs used to treat and prevent human immunodeficiency virus (HIV). Motivated by this, we investigated the radiation interaction properties of several HIV drugs to determine the interaction parameters, mass attenuation coefficient (MAC), atomic cross section (ACS), electronic cross section (ECS), effective atomic numbers (Zeff), and effective electron density (Neff). We calculated the values using the Phy-X/PSD software in the range of 0.015–15 MeV. Additionally, we calculated the exposure build-up factor (EBF), and energy absorption build-up factor (EABF) values of the drugs up to 40 mean free path (MFP) using the geometric progression (G-P) method. From our findings, we determined that Combivir, with its relatively high heavy element content, had the highest radiation attenuation capacity, whereas the probability of Lopinavir interacting with photons was the lowest compared with the other drugs. The results of the EBF and EABF parameters, including the scattering effects, ordered the drugs opposite to the primary interaction parameters such as MAC, ACS, ECS, and Zeff. These findings can guide the treatment process of HIV-positive patients and inform HIV prevention practices conducted alongside radiotherapy, as the interaction between radiation and a drug may cause deterioration in the drug's structure.

Investigation of radiation protective features of azadispiro derivatives and their genotoxic potential with Ames/Salmonella test system

Purpose Five different types of synthesized azadispiro derivatives have been analyzed for radiation absorption capacity and determined their potential to be exploited as substances for a drug to be developed against radiation has been investigated. Material and methods Fast neutron attenuation parameters like the effective mean free path, half-value layer (HVL), removal cross-sections, and neutron transmission number were found with the Monte Carlo simulation Geometry And Tracking (GEANT4) code. Gamma radiation absorption parameters, such as effective atom number (Z eff), mean free path (MFP), mass attenuation coefficient (MAC), and half-value layer (HVL) were theoretically determined with WinXCom software. Besides, the exposure build-up factor (EBF) was calculated by using GP fitting parameters. Neutron absorption dose rate was experimentally calculated with 241Am-Be fast neutron source which has 4.5 MeV of energy, 74 GBq activity, and portative BF3 neutron detector. Ames/Salmonella test systems were used for the genotoxic potentials of the azadispiro derivatives Results and conclusions Experimental and theoretical results were checked with paraffin and High-Density Polyethylene. The results showed that Azadispiro derivatives have neutron radiation absorption capability close to paraffin and High-Density Polyethylene. The gamma radiation absorption properties for azadispiro derivatives have been investigated, and it has been observed that these materials can absorb gamma radiation. Ames/Salmonella assay was used to examine whether the derivatives had a genotoxic effect probability or not. The results showed that these derivatives were genotoxic and safe at test doses (up to 5 mM). Consequently, it has been understood that these azadispiro derivatives can be used as active and genotoxic safety ingredients in the production of a protective drug against both neutrons and gamma rays.

Radiation shielding and dosimetric parameters of mexican artisanal bricks

In this work, were determined some radiation shielding and dosimetric parameters of three types of bricks for photons energy from 1 keV to 100 GeV photons using the Phy-X/PSD software, and for comparison also has been calculated the same parameters for NBS concrete. The parameters calculated are the linear attenuation coefficients (LAC), effective atomic numbers (Zeff), half value layers (HVL), the energy absorption buildup factors (EABF) and the exposure buildup factors (EBF), as well as the coefficients to use the geometric progression (G-P) fitting method. Obtained results show that the three types of bricks can be used safely for the design of medical facilities housing mammography units (less than 30 keV).

Structural, optical, and radiation shielding features of newly developed BaZrO3/Na2O–B2O3 glass

In this work, the radiation shielding capacity of novel BaZrO3 perovskite-doped sodium borate glasses with compositions of 40Na2O–60B2O3+ x BaZrO3 (where x = 0, 10, 20, and 30% wt.) was examined. XRD and FTIR have been used to analyze the structural characteristics of the produced glass systems. The relative concentration of BO4 units in the sodium borate glass N4 decreased by adding 10% from BaZrO3 and then increased. Also, the optical energy increases from 3.2 eV to 3.34 eV as the BaZrO3 content reaches 10% and then drops to 3.15 eV with an increase in the BaZrO3 content to 30%. Further, glasses' electronic polarizability, reflection loss, and optical transmission were investigated. The gamma-radiation shielding characteristics of novel BaZrO3-based glasses were experimentally investigated. The MAC values enhanced from 0.0534 cm2/g for NB glass to 0.0685 cm2/g for NB+30% BaZrO3 at the energy of 1.333 MeV. Furthermore, the experimental and theoretical findings for mass attenuation coefficient (MAC) have also been compared utilizing Phy-X/PSD software. In addition, the exposure build-up factor (EBF), removal cross-sections of fast neutrons, and equivalent atomic numbers (Zeq) have been computed. According to the results, adding BaZrO3 perovskite seems to boost the gamma-ray shielding effectiveness of sodium borate glass.

Pre-clinic study of radiopharmaceutical for Covid-19 inactivation: Dose distribution with Monte Carlo Simulation

Monte Carlo simulation method and Nuclear Medicine MIRD method were used to evaluate the effect of radiopharmaceuticals on Covid-19 disease. The mean absorbed organ dose in the target organ and gamma radiation emitter attenuation properties such as linear attenuation coefficients, energy absorption build-up factors (EABF), exposure build-up factors (EBF), and relative dose distributions (RDD) were examined. The results showed that radiopharmaceuticals containing gamma radiation emitters which are densely ionizing charged particles induced membrane damage and produced protein damage.

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

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

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

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