Search

Diketone derivatives have significant medicinal actions, in particular their anti-cancer properties. In the present investigations, gamma and neutron interaction parameters such as MAC, Zeff, Zeq, EABF, and EBF of the diketone derivaties such as DKD1 (C17H10O5), DKD2 (C27H23NO4), DKD3 (C41H43NO4), DKD4 (C33H48O2), DKD5 (C30H34O2), and DKD6 (C32H35NO2) were studied using EpiXS and NGCal software. The EBF and EABF increase with increasing MFP values, shifting the peak position from a lower to a higher energy region. The results suggest that diketone derivatives such as DKD1 have good gamma absorption and DKD4 have good neutron absorption samples. [ABSTRACT FROM AUTHOR]

This report presents a theoretical investigation of the shielding and radiation dosimetry parameters of two perovskite semiconductors defined by Na2CuMCl6 (M = Bi (NCSC1) and Sb (NCSC2)). Photon interaction parameters such as the mass attenuation coefficient μ / ρ , effective atomic number Z eff , effective electron density N eff , mass energy absorption coefficient μ en / ρ , specific gamma constant Г, absorbed gamma dose rate D r , energy absorption (EABF), and exposure (EBF) buildup factors were computed following standard procedure for discrete photon energies (0.2, 0.662, and 1.25 MeV). The magnitudes of μ / ρ vary between 0.0534 and 0.1881 cm2/g and 0.0565 and 0.4863 cm2/g for NCSC1 and NCSC2, respectively. The values of Z eff fell within the ranges 20.60–25.82 and 25.41–51.37, for NCSC1 and NCSC2, respectively. The corresponding ranges for N eff were 2.79–3.5 × 1023 electrons/g and 2.88–5.82 × 1023 electrons/g. The values of Г for energies between 0.2 and 1.25 MeV are within 10.9–20.42 Rm/Cih and 17.61–23.94 Rm/Cih for NCSC1 and NCSC2, respectively. Comparatively, NCSC2 has lower photon buildup factors across the energies compared to NCSC1.Based on the analysis of all evaluated photon interaction parameters, it can be deduced that NCSC2 had higher photon shielding potentials than NCSC1in both broad and narrow beam photon transmission scenarios. In a comparison of the photon absorption competences of the NCSC perovskite semiconductors with those of the RS series commercial glass shields, the NCSC semiconductors showed promising potential as a Pb-free gamma photon absorber in nuclear technological applications. The NCSC semiconductors are attractive as environmentally friendly shields for low photon energy attenuation. The semiconductors are therefore recommended for shielding of laboratory radiation sources and for the protection of radiation-sensitive electronic components. [ABSTRACT FROM AUTHOR]

In this work, four waste paper composites were studied in terms of several photon interaction parameters over the energy region from 0.015 to 15.0 MeV. The waste paper and natural rubber (WP/NR) composites of different densities ranging from ρ = 0.894 to 1.16 gm⋅cm-3 were used for shielding radioactive rubble at different time period stages. Some additives were also used including high-abrasion furnace black, paraffin wax, B4C, as well as magnetite. The deduced parameters of photon interaction: equivalent atomic number Zeq, exposure buildup factor and energy absorption buildup factor have been studied as a function of incident photon energy, WP/NR elemental composition, and for penetration depths, up to 40 mean free path. The Zeq numbers have shown slight variation over the selected incident energy range and buildup factors were found to be modest at low and high photon energy meanwhile their values increase widely over the intermediate energy region. In addition, kerma relative to air for photon energies from 1 to 20 MeV were computed and show dependence upon equivalent atomic numbers. In this work, it was clear that filled samples offer better shielding capabilities than unfilled ones. The obtained data could be useful for radiation physicists and scientists in estimating the γ-irradiation received after applying such shields.

The mass attenuation coefficient (MAC), effective atomic number (Zeff), equivalent atomic number (Zeq), fast neutron removal cross-section (FNRCS), energy absorption buildup factor (EABF), mass-energy absorption coefficient (MenAC), relative kerma, and computed tomography (CT) numbers were calculated for the alginates, bisphenol A-glycidyl methacrylate (Bis-GMA), chitin, hyaluronic acid, polycaprolactone (PCL), polyether ether ketone (PEEK), polyethylene glycol (PEG), polyglycolide (PGA), polylactic acid (PLA), poly lacto-co-glycolic acid (PLGA), poly methyl methacrylate (PMMA), poly vinyl alcohol (PVA), polyvinylpyrrolidone (PVP), triethylene glycol dimethacrylate (TEGDMA), and urethane dimethacrylate (UDMA) polymers using the Phy-X/PSD and Py-MLBUF software. The total stopping power (TSP) of electrons, protons, and alpha particles was calculated for the selected polymers using the ESTAR, PSTAR, and ASTAR programs. The effective atomic number for absorption and charged particle (electron, proton, alpha, and carbon ion) interactions were estimated for the selected polymers using Phy-X/ZeXTRa software. The FNRCS values of Bis-GMA, PCL, PEG, PMMA, and PVP were similar to those of the human tissues. For the selected polymers, the Zeff values for electron, proton, alpha, and carbon ion interactions of PCL, PEG, PLGA, and PVA were similar to those of human tissues, except for the cortical bone, across the entire energy range. These results are expected to assist in selecting suitable polymers as tissue-equivalent materials in the desired energy range for photon, neutron, and charged-particle interactions. This study is expected to be useful for radiation therapy and dosimetry. [ABSTRACT FROM AUTHOR]

With a composition (in mol %) of 29Bi2O3-70B2O3-(1-x)Cr2O3: xZnO, (where, x = 0, 0.5 and 1) three glass samples were prepared by melt-quenching process. Despite the addition of ZnO nanoparticles, the SEM- morphology studies showed that the synthesized samples were transparent glass-ceramics. XRD studies confirmed that ZnO nanoparticles were homogeneously distributed in the glassy phase. When ZnO nanoparticles were added, oxygen packing density (OPD) was observed to increase, whereas boron-boron separation (dB-B) gradually decreased. The Raman spectra demonstrated that there was transformation of primary glass forming units, [BO3] → [BO4] units from x = 0 to 1 mol% of ZnO nanoparticles in the composition. Two absorption bands (in blue and red regions) have been attributed to the d-d transitions of Cr3+ ions in octahedral symmetry sites. When ZnO nanoparticles were added in the composition, the bandgap (Eo) was found to increase, and the non-linear optical susceptibility (χ(3)) decreased. Various gamma ray shielding properties of the samples have been determined in the energy range of 1 keV–15 MeV with the help of the Windows based program EpiXS. The sample with highest concentration of ZnO nanoparticles in the composition showed better radiation shielding behaviour among the three samples.

In order to identify the importance of perovskites in nuclear science, studies aimed at obtaining the radiation interaction quantities of perovskites are essential. This study computed and analyzed the gamma photon interaction parameters of CaCu 3 B 2 Re 2 O 12 (B Mn, Fe, Co, and Ni) perovskites to reveal their shielding potentials and comparative advantages against traditional shielding materials. Four samples of ferrimagnetic quaternary perovskites whose chemical structures are summarized as CaCu 3 B 2 Re 2 O 12 (B Mn (CCMRO1), Fe (CCMRO2), Co (CCMRO3), and Ni (CCMRO4)) were considered for their gamma interaction quantities. The values of mass attenuation coefficient (μ ρ) was calculated with XCOM and they were in the range of 0.0552 cm2/g–0.4162 cm2/g for CCMRO1, 0.0553 cm2/g–0.4165 cm2/g CCMRO2, 0.0552 cm2/g–0.4148 cm2/g for CCMRO3, and 0.0555 cm2/g–0.4163 cm2/g for CCMRO4. The values of effective atomic number and electron density was within the range 21.38–43.38 and 2.84 x 1023 electrons/g −5.62 x1023 electrons/g, respectively. The trend of the mass energy absorption coefficients of the perovskites was also found to be in the same order as the mass attenuation coefficient. CCMRO3 has the highest photon energy absorptive ability among the perovskites while CCMRO2 has the least capacity. Also, the gamma dose rates in15 mm thick of CCMRO1, CCMRO2, CCMRO3, and CCMRO4 for 1.25 MeV are about 1446 kR/h, 1449 kR/h, 1453 kR/h, and 1446 kR/h, respectively. Comparatively, the values of the exposure and energy absorption buildup factors were almost the same for the perovskites at the same energy and optical depth. The investigated perovskites had higher mass attenuation coefficients that standard shielding glasses. The perovskites can be used for shielding or any other radiation absorption roles in radiation science and technology, especially for photons at low energies. • Newly developed gamma shielding perovskites is reported. • Radiation attenuation properties are studied. • Monte Carlo simulations are carried out. • A good agreement between the theory and the simulation. • CCMRO4 sample has a potential use in radiation applications. [ABSTRACT FROM AUTHOR]

Gamma-ray shielding properties of eight different metallic glasses based on CuxZr100-x: x = 35 (Cu35Zr65) − 70 (Cu70Zr30) were determined using Monte Carlo simulations and Phy-X/PSD software. A typical gamma-ray transmission setup has been modeled in MCNPX Monte Carlo code. The general trend of the linear attenuation coefficients (μ) was reported as (μ)Cu35Zr65 < (μ)Cu40Zr60 < (μ)Cu45Zr55 < (μ)Cu50Zr50 < (μ)Cu55Zr45 < (μ)Cu60Zr40 < (μ)Cu65Zr35 < (μ)Cu70Zr30. In terms of half value layer (HVL) values, the Cu35Zr65 sample has the highest value (2.984 cm) and the Cu70Zr30 sample has the lowest value (2.769 cm) at 8 MeV photon energy. The mean free path (MFP) values were 4.305 and 3.995 cm for Cu35Zr65 and Cu70Zr30 samples, respectively. Generally, MFP and HVL values of the studied glasses were reported as (MFP,HVL)Cu35Zr65 > (MFP,HVL)Cu40Zr60 > (MFP,HVL)Cu45Zr55 > (MFP,HVL)Cu50Zr50 > (MFP,HVL)Cu55Zr45 > (MFP,HVL)Cu60Zr40 > (MFP,HVL)Cu65Zr35 > (MFP,HVL)Cu70Zr30 for all photon energy range. The Cu70Zr30 sample showed maximum values of both the effective conductivity (C eff) and effective electron density (N eff). In addition, the Cu70Zr30 sample has minimum exposure and energy absorption buildup factor (EBF and EABF) values at all studied gamma-ray energies. The results revealed that the Cu70Zr30 sample has superior attenuation properties among all studied samples.

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 (X(1)) increased from 0.370 to 0.397. The nonlinear optical susceptibility (X³ ) and nonlinear refractive index n2 optical 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 ( Σ) 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. [ABSTRACT FROM AUTHOR]

Copyright of Nuclear Physics & Atomic Energy is the property of National Academy of Sciences of Ukraine, Institute for Nuclear Research and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)

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. [ABSTRACT FROM AUTHOR]

This study focuses on simulation of the radiation shielding parameters for nickel-based superalloys: Inconel 600, 718 and 725 superalloys. The partial interactions, mass attenuation coefficient value (µm), effective atomic number value (Zeff), effective electron density value (Nel) and half value layer (HVL) at photon energy ranging of 1 keV–100 GeV, were estimated theoretically by WinXCom software program. Moreover, buildup factors (energy absorption buildup factor and exposure buildup factor) were determined using geometrical progression (G-P) fitting method for energy ranging 0.015–15 MeV at deep penetration 1–40 mfp (mean free path).Also, fast neutron removal cross sections (ΣR) were simulated by partial density method at energy ranging from 2 to 12 MeV. The results found that nickel-based superalloy Inconel 725 had excellent radiation shielding property. The study also brings the significance of these samples by comparing with standard commercial concrete. [ABSTRACT FROM AUTHOR]

In the present study, Energy Absorption Buildup Factor (EABF) and Exposure Buildup Factors (EBF) of the CR-39 and Trivex optical lenses are calculated by using the Geometric Progression (GP) fitting method based on ANSI/ANS-6.4.3 database. The study analyses comprehensively for different penetration depths within the energy range of 0.015 - 15 MeV up to 40 mfp. The buildup factors are calculated in the examined materials depending on the photon energy that arrives, the penetration depths, and the chemical composition of the material reach at maximum values in the energy region where inconsistent scattering interaction probabilities are intensive. The results show that the CR-39 optical lens had better radiation shielding performance. The suitability of the results is compared with the powerful software tools (EPICS2017 and Phy-X/PSD), which are preferred frequently in the literature to calculate radiation shielding parameters. It is found that the relative changes between the EPICS2017 and Phy-X/PSD software compared with the results of this study are about 8% and 9% for the CR-39 and Trivex optical lens, respectively. This indicates that the results from the study are in good agreement. [ABSTRACT FROM AUTHOR]

In this research, a series of (100–x)TeO2–xWO3 glass systems (where x = 0, 10, 20, 30, 40 and 50 mol%) have been simulated in terms of radiation shielding behaviors. The simulation of mass attenuation coefficients (μm), effective atomic numbers (Zeff) and effective electron densities (Nel) were calculated by WinXCom software program at energies ranging from 1 keV–100 GeV. The method of geometric progression (G–P) fitting has been used to calculate at wide energies ranging from 15 keV–15 MeV and up to 40 penetration depths (mfp) for buildup factors: exposure and energy absorption buildup factors (EBF and EABF). The simulated data reports that WO3 partial replacement of TeO2 in glass system (100–x)TeO2–xWO3 which increases behavior of radiation attenuation and 50TeO2–50WO3 showed the best shielding properties and potential to use as a transparent shielding material. [ABSTRACT FROM AUTHOR]

Copyright of Adiyaman University Journal of Science & Technology / Adıyaman Üniversitesi Fen Bilimleri Dergisi is the property of Adiyaman University, Institute of Science / Adiyaman Universitesi Fen Bilimleri Enstitusu and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)

Novel multiple glassy composite materials were offered for gamma shielding applications, photovoltaic applications, nuclear engineering, etc. as an alternative to concrete and pure lead. Studied glassy composite materials demonstrated better gamma-ray shielding than ordinary glass and concrete in the 15 keV–15 MeV energy range. The multiple composites were prepared with (xA + 0.11B + 0.02C + (0.87− x)[(1 − y)D1 + yD2] = 1) recipe. BXCOM software was used to calculate exposure buildup factors (EBFs), energy absorption buildup factors (EABFs), and effective atomic numbers (Zeff). Monte Carlo simulations were performed via MCNP 6.2 code to evaluate the important shielding factors like mass attenuation coefficients (µm), half-value layers (HVLs) and compared with XCOM results. The quinary composites were compared in each step with each other to determine which component is better for radiation shielding [(Cr2O3/Na2O/MnO2), Sb2O3, B2O3, V2O5, and Fe2O3]. From the investigated ratios, Cr2O3 and MnO2 at 85%, and Na2O at 70% were evaluated to be the best ratios to reduce radiation dose in the incident energy range. Also, Fe2O3 addition at 10% enhanced shielding ability. According to the simulation results, the quinary MnO2 composite (MnO2/Sb2O3/B2O3/V2O5/Fe2O3) was determined to have the best shielding property among all the studied composites. A gamma spectroscopy system with NaI(Tl) detector was used to determine the shielding properties of this best material, experimentally. All the studied composites indicate better gamma shielding properties than concrete, some of them are approaching pure lead. [ABSTRACT FROM AUTHOR]

In this present work, the gamma-ray radiation shielding parameters of nine different FexCr1-x. and FexNix alloys that were prepared at different mixture rates have been investigated. The gamma-ray shielding has different parameters which are total mass attenuation coefficient (µt), effective atomic number (Zeff) and effective electron density (Neff), half-value layer (HVL), tenth value layer (TVL), exposure buildup factor (EBF), energy absorption buildup factor (EABF) components. These shielding parameters have been measured experimentally by using gamma photons in the energy range from 0.0175 MeV to 0.05954 MeV. WinXCOM, ParShield and Phy-X program results were compared with values from experimental measurements used in characterizing the radiation shielding properties. The experimental mass attenuation coefficient values are in good concordance with the WinXCOM evaluations, with ranging from 0.04 to 13.21%. Also, the mass attenuation coefficient values derived using the ParShield and Phy-X simulations program have compared with WinXCOM. These values are quite agreed with the WinXCOM values. Additionally, in this work, the radiation shielding parameters are calculated by using experimental values and deviated values of theoretical calculations of WinXCOM, ParShield and Phy-X. It has been determined that the theoretical calculation programs are quite compatible. While some of the experimental radiation absorption findings almost exactly overlapped with the WinXCOM values, it was observed that there were acceptable differences with the ParShield and Phy-X values. [ABSTRACT FROM AUTHOR]

Apatite-wollastonite (AW) is an important biomaterial useful in clinical practice for tissue engineering and other applications. In this research paper, AW and B 2 O 3 -doped AW glass ceramics (GCs) were reported and investigated deeply by means of their ability to attenuate gamma-photons. The studied samples denoted by AW, AW-10B, and AW-20B as the B 2 O 3 content from 0 to 20 mol% with the step of 10. Using FLUKA and other theoretical approaches, photon interaction parameters for narrow and broad beam transmission through the AW GCs were estimated for the 15 keV–15 MeV energy range. Also, the density of the GCs increased as the B 2 O 3 content increased. The mass attenuation coefficients were found to be within the ranges 0.0231–13.5659 cm2/g, 0.0225–12.3561 cm2/g, and 0.0220–11.1079 cm2/g for AW, AW-10B, and AW-20B, respectively. The effective atomic number of the GCs fell within the range 11.04–17.26, 10.88–17.01, and 10.21–16.72, respectively. As the doping concentration of B 2 O 3 increased, the gamma energy that the AW GCs were able to absorb decreased. The addition of B 2 O 3 compromised the photon shielding competence of AW in both narrow beam and broad beam scenarios. The GCs had better photon-absorbing competence than some existing gamma-photon shields. The GCs may thus be used as photon absorbers in clinical practice or in other nuclear applications. • Gamma attenuation of AW ceramic system is reported. • Experimental work is carried out. • Monte Carlo simulations are employed. • Dose rate and buildup factors are evaluated. • GCs had better photon-absorbing competence. [ABSTRACT FROM AUTHOR]

The coconut dust gypsums were fabricated and investigated through shielding radiation properties, energy absorption buildup factor (EABF), and exposure buildup factor (EBF). The mass attenuation coefficient (µm) was investigated by using the Compton scattering technique at energy 662 keV and theoretical values of the mass attenuation coefficients were computed by using the WinXCom software program at different photon energies from 1 keV - 100 GeV. EABF and EBF values were computed by the Geometric Progression (G-P) fitting method at photon energies ranging between 0.015 and 15 MeV up to deep penetration of 40 mean free path (mfp). After the addition of coconut dust volume into gypsum board, it was found that µm values of the experiment and theory were generally in a good agreement. The results also indicated that the µm increased while the EABF and EBF decreased along with the increase in the coconut dust volume. The EABF and EBF values with photon energy and deep penetration for coconut dust gypsums were found at a minimum value, i.e., at low and high energy range whereas, at the intermediate energy range, it could become high. These results suggest that coconut dust gypsums can be used as shielding radiation building material. [ABSTRACT FROM AUTHOR]

Dense glasses in the binary bismuth-borate system, x Bi 2 O 3 -(1- x)B 2 O 3 (BBO), x = 0.25, 0.5, & 0.75 were prepared by conventional melt-quenching process at different temperatures. The melt was hot pressed between the stainless-steel plates to obtain dense glasses. The glasses obtained were optically clear, thermally stable and amorphous in nature. Transparent BBO glasses exhibited high density in the range of 5.5–8.29 g/cm3 which is attributed to the high bismuth content and pressure induced compaction at high temperatures in the hot-pressed quenching. Gamma radiation shielding properties of the dense BBO glasses were investigated by calculating mass attenuation coefficients, effective atomic number, and different buildup factors. Radiation shielding properties were calculated using the XCOM and Phy-X web software as a function of photon energy for all the glasses. Experimental mass-attenuation coefficients at different energies of the BBO glasses were determined through radiation transmission method. Measured mass-attenuation coefficients of the BBO glasses were in close agreement with the calculated values. Further, exposure and energy absorption buildup factors of the dense BBO glasses were studied at different penetration depths as a function of the photon energy. The results were compared with the heavy-metal oxide glasses reported in the literature and with respect to lead metal shield. Dense binary bismuth glass exhibited high mass-attenuation coefficients, and low half-value layer, and mean-free path which are comparable with the metal lead. The dense binary bismuth borate glasses reported here can be the excellent radiation shielding transparent simple glass system and promising for the radiological applications. [ABSTRACT FROM AUTHOR]

In this study, nuclear radiation shielding features of Al2Si2O5(OH)4–KAlSi3O8–SiO2 ceramic systems were explored by depending on cobalt (Co) insertion ratio (0, 5, 10, 20, 30 wt%). For this aim, five ceramic samples were produced and their elemental compositions were obtained with SEM-EDX analysis. Then, transmission measurements were achieved by using an ultra Ge detector and photons with 0.081–0.383 keV energy ranges. From the evaluated transmission spectra, mass attenuation coefficient (μρ) values of five ceramics were obtained experimentally and compared with theoretical results. According to the outcomes, the increment of the Co insertion rises the μρ values, whereas the half-value layer (HVL) value declines. It is also observed that effective atomic number (Zeff) values are raised, while effective electron density (Nel) is declined as Co additive increases in the ceramic sample. The geometric progression (GP) approach was utilized to estimate the energy absorption buildup factor (EABF) and exposure buildup factor (EBF) for the produced ceramic samples. EABFs and EBFs were obtained to be the smallest for 30% doped S5 sample according to the other ceramic samples. Lastly, the neutron attenuation ability of the ceramic samples was interpreted by finding the effective neutron cross sections (ΣR). It is noticed that the ΣR values are almost similar for all of the ceramics. As a result, the S5 sample is a skilled nominee for photon and neutron protection applications among the fabricated ceramic samples. [ABSTRACT FROM AUTHOR]

The preparation of materials with high attenuation performance is one of the major issues in the radiation shielding applications. This study is based on the investigation of gamma-shielding performances of various polyester composites reinforced with Zn. Utilizing gamma spectrometer based on HPGe detector, the mass attenuation coefficient (μ/ρ) of the present composites was measured at various photon energies between 59.5–1408 keV. The obtained experimental data were confirmed with those of MCNPX code as well as XCOM program. It is found that the attenuation coefficient values of the studied composites are in good agreement with the results of other approaches at the investigated energies. The best photon-shielding effectiveness was observed in the composite tagged with Zn (10%). The shielding characteristics of composite enhances with the addition of Zn as filler. [ABSTRACT FROM AUTHOR]

In this study, 60KAlSi 3 O 8 +10Al 2 Si 2 O 5 (OH) 4 +(30-x)SiO2+xA 2 O 3 (x = 0, 10, 20, 30 wt% and A = Tm, Dy) ceramics were produced by conventional method to determine their usability as shielding material against ionized gamma radiation. To investigate the ionized photon shielding properties of the fabricated materials, the photon intensities (I and I 0) were experimentally measured at 81, 160, 223, 302, 356, and 383 keV energies emitted from 133Barium radioisotope, and then the mass attenuation coefficient (μ ρ), The linear attenuation coefficients (μ, cm−1), half-value thickness (Δ 0.5), mean free path (λ), effective atomic numbers (Z eff) and electron densities (N el) were derived experimentally. The obtained results were benchmarked with the calculated values from the EpiXS program. Also equivalent absorbed dose (EAD) values for fast neutrons were measured using BF3 gas proportional neutron detector from the Canberra NP-100B series and a241Am/Be neutron source with a 10 mCi activity. In addition, fast neutron shielding parameters (Σ R) of ceramics were also computed theoretically. The density of the fabricated ceramics varied from 2.607 g/cm3 to 4.392 g/cm3 when the Tm 2 O 3 was raised from 0 wt% to 30 wt%. Likewise, with the addition of Dy 2 O 3 compound, the densities of ceramics varied between 2.607 g/cm3 to 4.152 g/cm3. It was found that nuclear radiation shielding properties evolved by adding Tm 2 O 3 and Dy 2 O 3 compounds in the present ceramic. • Gamma shielding parameters of new type of ceramics were investigated. • Experimental and theoretical μ ρ , μ, Δ 0.5 , λ, Z eff and N el were derived. • And also neutron shielding parameters were investigated. • Buildup factors of the ceramics were calculated by EpiXS program. • Tm30 ceramic containing 30% Tm 2 O 3 compound is the best shield. [ABSTRACT FROM AUTHOR]

This research presents a new Windows compatible program (EXABCal) for photon exposure and energy absorption buildup factors for standard energy grid from 0.015- 15 MeV for elements, mixtures and compound. This program was written using Python programming language and the calculation of buildup factors was based on the well-known Geometric Progression (GP) fitting procedure. The equivalent atomic numbers and GP fitting parameters of mixtures and compounds can also be evaluated using this program. The program has been used to evaluate the photon exposure and energy absorption buildup factors for standard energy grid from 0.015- 15 MeV for water, air and concrete, compared with values from the American Nuclear Society (ANS) standard reference data (ANSI-6.4.3) and found to be of high accurate with minimal errors. The program is fast and easy to use and will be of valuable interest to medical Physicist, radiation Physicists, Radiation shielding design engineers, students, teachers and researchers and other experts working in areas where nuclear radiation is applied.

In the present research, standard ceramic and Molybdenum (Mo) doped ceramics were fabricated to determine the shielding properties against gamma and fast neutron radiation. The ceramics were exposed to photons with 81, 276, 302, 356, 383 keV energies emitted from 3 Ci 133Ba radioactive source and the photon intensities were detected by utilizing Ultra Ge detector. With the obtained results, the gamma shielding parameters; mass attenuation coefficients (μ ρ), the mean free paths (mfp), half value layers (HVL), tenth value layers (TVL), effective atomic numbers (Z eff) and effective electron densities (N el) were obtained experimentally and compared to the theoretical outcomes computed by utilizing WinXCOM program. It was found that, S4 ceramic containing 30% Mo element has higher μ ρ and Z eff value and lower MFP, TVL and HVL values than the other ceramics. The EBF and EABF values of S4 ceramic were lower than the values of other investigated ceramics. Thus, it has been concluded that the use of Mo element in ceramic increases the gamma shielding property of the ceramics. When the ceramics were examined in terms of fast neutron shielding, no important difference was found between the ceramics. Image 1 [ABSTRACT FROM AUTHOR]

The present investigation has been undertaken to evaluate gamma radiation shielding effectiveness of inorganic metal halide cubic perovskites CsBX 3 (B = Sn, Ge, Pb; X = I, Br, Cl). The values of mass attenuation coefficients (μ / ρ) were computed at the energy range of 1.00 keV–100 GeV by WinXCom computer code. Thereupon, half value layer (HVL), the effective atomic number (Z eff) and electron density (N el) are calculated by using μ / ρ values. Besides, energy absorption buildup factor (EABF) and exposure buildup factor (EBF) of inorganic metal halide cubic perovskites have been determined using the Geometric Progression (G-P) fitting method at energies 0.015–15 MeV up to penetration depths of 40 mean free path (mfp). The examined shielding parameters are highest in low energy region and lowest in the middle energy region. The results were discussed in relation to the contents of the samples. The lead-containing compounds are more efficient than the other compounds for shielding gamma radiations. Other perovskites (without lead) also have the ability to absorb radiation better than many other shielding materials currently used. Thus, the studied compounds may be effective in the production of novel shielding materials. • The photon shielding parameters of inorganic metal halide cubic perovskites were investigated. • Buildup factors of the compounds were calculated by G-P fitting method. • Lead-containing compounds are more effective than others for γ-ray. [ABSTRACT FROM AUTHOR]

This study is focused on the gamma rays and neutron interaction with the different Er +3 concentrations of (2ErCl 3 -98SiO 2 , 4ErCl 3 -96SiO 2 , 6ErCl 3 -94SiO 2 and 8ErCl 3 -92SiO 2 ) EDFA amplifiers. To provide the enough information of these compounds for design and applications of radiation shielding materials in different applications in nuclear engineering and technologies. The radiation protection for optical amplifier is an important role to obtain high gain. The XCom program has been used to calculate the mass attenuation coefficients (μ m ), half value layer (HVL) and mean free path (MFP) in the energy range 1 keV–100 GeV of four different Er +3 concentrations of EDFA amplifiers. The Exposure Buildup Factors (EBF), gamma ray energy absorption (EABF) and fast neutron removal cross-section (∑ R ) have been computed. The EBF and EABF calculations are done for a range up to 15 MeV with penetration depths up to 40 mfp. The results indicated that EDFA with 8 mol % of Er +3 is the superior gamma-ray shielding. This work may be beneficial for signal nuclear radiation protection, dose evaluation and other shielding requirements. [ABSTRACT FROM AUTHOR]

Gamma rays shielding effectiveness of newly developed Tellurium oxide based-glasses have been investigated. We have used Geometric Progression (G-P) fitting method for calculating the absorption (EABF) and exposure (EBF) buildup factors at energies 0.015–15 MeV. The buildup factors were found to depend strongly on the photon energy and mean free path ( mfp ). The EABF and EBF indicated that these types of glasses are suitable for shielding effectiveness and becoming more superior as the molar fraction of WO 3 is increased in the glass compound. The present work should be useful for a possible utilizing of these glasses for optical and medical applications where radiation exposure is present. [ABSTRACT FROM AUTHOR]

The gamma ray energy absorption (EABF) and exposure buildup factors (EBF) of (100-x)TeO 2 -xB 2 O 3 glass systems (where x=5, 10, 15, 20, 22.5 and 25 mol%) have been calculated in the energy region 0.015–15 MeV up to a penetration depth of 40 mfp (mean free path). The five parameters (G-P) fitting method has been used to estimate both EABF and EBF values. Variations of EABF and EBF with incident photon energy and penetration depth have been studied. It was found that EABF and EBF values were higher in the intermediate energy region, for all the glass systems. Furthermore, boro-tellurite glass with 5 mol% B 2 O 3 , was found to present the lowest EABF and EBF values, hence it is superior gamma-ray shielding material. The results indicate that the boro-tellurite glasses can be used as radiation shielding materials. [ABSTRACT FROM AUTHOR]

Comparative study on various deterministic methods and formulae of double layered transmission exposure buildup factors (DLEBF) for point isotropic gamma-ray sources has been performed and the results are provided here. This investigation has been performed on some commonly available engineering materials for the purpose of gamma-ray shielding. In reality, the presence of air around the gamma-ray shield motivated to focus this study on exposure buildup factor (EBF). DLEBF have been computed at four energies viz. 0.5, 1.0, 2.0 and 3.0 MeV for various combinations of the chosen five samples taken two at a time with combined optical thickness up to 8 mean free path (mfp). For the necessary computations for DLEBF, a computer program (BUF-toolkit) has been designed. Comparison of Monte Carlo (EGS4-code) and Geometric Progression (G.P.) fitting point kernel methods were done for DLEBF computation. It is concluded that empirical formula given by Lin and Jiang using EBF computed by G.P. fitting formula is the most accurate and easiest method for DLEBF computations. It was observed that DLEBF values at selected energies for two layered slabs with an orientation (low- Z material followed by high- Z material) were lower than the opposite orientation. For optical thickness up to 8 mfp and chosen energy range (0.5–3.0 MeV), Aluminum-Lime Stone shield, appears to provide the best protection against the gamma-rays. [ABSTRACT FROM AUTHOR]

Photon buildup for some SrSO, BaSO, MgSO, MnSO, FeSO and ZnSO thermoluminescent dosimetric (TLD) compounds was investigated in the present work. Photon energy absorption buildup factors and photon exposure build factors were computed for the TLD compounds using the five-parameter geometric progression fitting method in energy range 0.015-15 MeV for penetration depths up to 40 mean free path. The buildup factors were studied as a function of photon energy, penetration depth and chemical compositions. Effective atomic numbers and air-kerma for the TLD compounds were calculated and ICRU standard tissue equivalence was discussed. [ABSTRACT FROM AUTHOR]

Neutron dose transmissions for fast neutrons produced by 5.486 MeV alpha particles on beryllium are measured in concrete samples with and without limonite ore to investigate their neutron shielding qualities. Using measured values, macroscopic removal cross-sections (Σ R , cm −1 ) have been determined experimentally and also Σ R values have been calculated theoretically using the elemental composition of the concrete mixes. The best neutron shielding property of concrete sample containing 100% limonite ore (FCL: fine and coarse limonite) was found. Additionally, energy absorption buildup factor (EABF) and exposure buildup factor (EBF) of concrete sample were calculated using the five-parameter Geometric Progression (G-P) approximation in the energy range of 0.015–15 MeV for penetration depths up to 40 mean free path (mfp). The incident photon energy and penetration depth dependence of buildup factors were examined. Finally, we observed that concrete samples have maximum values of buildup factors in the intermediate energy region around 0.1–0.3 MeV. FCL has the minimum values of both of the buildup factors. FCL has the excellent gamma shielding properties compared to the concrete samples. [ABSTRACT FROM AUTHOR]

In this study, certain photon absorption parameters including the energy absorption buildup factor (EABF) and exposure buildup factor (EBF) have been investigated for three different basalt samples collected from different parts of Van city. Radiation shielding properties of the basalt samples indicated a strong correlation between photon energy absorption parameters and values of EABF and EBF of basalt samples. It was found that EABF and EBF parameters are related to radiation shielding properties of basalt samples. A new method and algorithm based on ZXCOM was used. Instead of calculating G – P fitting parameters for every effective atomic number ( Z e f f ), EABF and EBF were calculated for Z e f f by interpolation, using ANSI/ANS 6.4.3 standard data available for Z e f f . [ABSTRACT FROM AUTHOR]

Gamma ray exposure buildup factor (EBF) and neutron shielding efficiency of borate glass systems in composition (100 − x − y) NaBO− xPbO− yNiO (where x and y = 0, 2, 4, 6, 8 and 10 weight percentage) were investigated in the present study. Gamma ray EBF values were computed using Geometric Progression (G-P) method for photon energy 0.015 to 15 MeV up to penetration depths of 40 mfp (mean free path). The macroscopic effective removal cross-sections (Σ) for fast neutron (2 to 12 MeV) were calculated. At low- and high-energy region, the EBF values were found minimum whereas maximum in the intermediate-energy regions with a sharp peak below 100 keV for oxide containing glass samples. The investigation was carried out for potential applications of borate glasses for radiation shielding. [ABSTRACT FROM AUTHOR]

Effective atomic numbers Z, air-kerma and energy-absorption buildup factors, EABF for some human organs and tissues, vitamins and tissue substitutes have been computed in the present work. Geometric-Progression (G-P) fitting method was applied for computation of EABF. It is observed that the EABF and air-kerma are dependent upon Z and chemical compositions. The EABF, Z and air-kerma of calcium carbonate and lithium carbonate are found in good agreement with cortical bone and fat, respectively. The EABF in the present work could be useful in medical diagnostics, radiation therapy procedures and also personal monitoring. [ABSTRACT FROM AUTHOR]

Radiation shielding performance against gamma rays for four mineralized natural rock samples collected from Um Bogma area, Southwestern Sinai, Egypt was determined by Monte-Carlo simulation, theoretical calculations and confirmed by experimental evaluations. The Monte Carlo simulation was utilized to investigate the shielding capacity of the investigated rock samples in the energy range between 0.015 and 15 MeV. According to the Monte Carlo simulation the best shielding properties were achieved for sample siltstone S22 which contains (Fe–Mn) mineralization and density of 3.85 (g/cm3), where the simulated linear attenuation coefficient decreased from 71.30 cm−1 to 0.09 cm−1, increasing the incident gamma photon energy between 0.015 and 15 MeV. On the other hand, the lowest gamma ray shielding capacity achieved for sample siltstone S24 which rich in iron sulfate, with linear attenuation coefficient decreased from 37.50 cm−1 to 0.05 cm−1, increasing the incident gamma ray energy between 0.015 and 15 MeV, respectively. The gamma ray shielding properties for sample siltstone S22 were examined experimentally to confirm the simulated results. Both of experimental and simulated results are close together, with a difference of ±0.5%. Moreover, the siltstone S22 sample shows a thin half-value layer, high effective and equivalent atomic numbers as well as low EBF and EABF values. • The gamma-ray shielding features were examined for four various types of rocks. • The Monte Carlo (MC) simulation was utilized to evaluate the collected rocks' shielding capacity. • The siltstone sample containing (Fe–Mn) mineralization has the best shielding capacity. • The experimental measurement was performed for the sample with MC's best gamma-ray shielding capacity. [ABSTRACT FROM AUTHOR]

Optically stimulated luminescence (OSL) materials are sensitive dosimetric materials used for precise and accurate dose measurement for low-energy ionizing radiation. Low dose measurement capability with improved sensitivity makes these dosimeters very useful for diagnostic imaging, personnel monitoring and environmental radiation dosimetry. Gamma ray energy absorption buildup factors and exposure build factors were computed for OSL materials using the five-parameter Geometric Progression (G-P) fitting method in the energy range 0.015-15 MeV for penetration depths up to 40 mean free path. The computed energy absorption buildup factor and exposure buildup factor values were studied as a function of penetration depth and incident photon energy. Effective atomic numbers and Kerma relative to air of the selected OSL materials and tissue equivalence were computed and compared with that of water, PMMA and ICRU standard tissues. The buildup factors and kerma relative to air were found dependent upon effective atomic numbers. Buildup factors determined in the present work should be useful in radiation dosimetry, medical diagnostics and therapy, space dosimetry, accident dosimetry and personnel monitoring. [ABSTRACT FROM AUTHOR]

Abstract: Human radiation exposure is increasing due to radiation development in science and technology. The development of radioprotective agents is important for protecting patients from the side effects of radiotherapy and for protecting the public from unwanted irradiation. Radioprotective agents are used to reduce the damage caused by radiation in healthy tissues. There are several classes of radioprotective compounds that are under investigation. Analgesics and anti-inflammatory compounds are being considered for treating or preventing the effects of damage due to radiation exposure, or for increasing the chance of survival after exposure to a high dose of radiation. In this study, we investigated the radioprotective effects of some analgesic and anti-inflammatory compounds by evaluating buildup factors. The gamma ray energy absorption (EABF) and exposure buildup factors (EBF) were calculated to select compounds in a 0.015–15MeV energy region up to a penetration depth of 40mfp (mean free path). Variations of EABF and EBF with incident photon energy and penetration depth elements were also investigated. Significant variations in both EABF and EBF values were observed for several compounds at the moderate energy region. At energies below 0.15MeV, EABF and EBF values increased with decreasing equivalent atomic number of the samples. In addition, EABF and EBF were the largest for ibuprofen, aspirin, paracetamol, naproxen and ketoprofen at 0.05 and 0.06MeV, respectively, and the EABF value was 0.1MeV for aceclofenac. From these results, we concluded that the buildup of photons is less for aceclofenac compared to other materials. [Copyright &y& Elsevier]

Abstract: Gamma and X-ray photon interaction parameters such as the equivalent atomic number (Zeq ), effective atomic number Zeff , and exposure and energy absorption buildup factor have been computed for some boron compounds in the energy range of 15–100keV. We have used WinXCom and ZXCom software to calculate the effective atomic number from Rayleigh/Compton (R/C) ratios. Finally, the selected boron compounds have been analyzed for application as radiation shielding materials. It is concluded that boric acid (M6) and concentrated colemanite (M1) have better shielding capability among the selected samples. [Copyright &y& Elsevier]