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In this research paper, we studied the optical and nuclear shielding efficiency of newly developed BGO glasses with the following compositions (in wt%): 32Bi 2 O 3 –68GeO 2 , 42Bi 2 O 3 –58GeO 2 , 47Bi 2 O 3 –53GeO 2 , 52Bi 2 O–48GeO 2 , 62Bi 2 O 3 –38GeO 2. BGO glasses were prepared by traditional melt quenching method. To obtain the band gap values of fabricated BGO glasses, optical absorption spectra were used for evaluation of optical properties. The mass attenuation coefficients (μ/ρ) were achieved for prepared glasses at 0.015–15 MeV photon energies employing MCNPX Monte Carlo code and WinXcom program. Moreover, broad-range of nuclear shielding parameters for gamma ray, neutrons and charged particles such as mass attenuation coefficient, half value layer, effective atomic number, buildup factors, mass stopping powers, projected ranges, fast neutron removal cross sections and damage factors were calculated. The refractive index is calculated from E opt , As Bi 2 O 3 concentration is enhanced, E opt is also increased as well as the optical electronegativity and consequently the refractive index. In addition, the results showed that BIGE5 glass sample with highest Bi 2 O 3 contribution has excellent nuclear radiation shielding ability among the other fabricated glass samples. [ABSTRACT FROM AUTHOR]

Four sulfide compounds' attenuation features of gamma-ray (Ag 2 ZnSnS 4 , Ag 2 ZnSnSe 4 , ZnS, and Ag 2 S) were described in this paper by a new software Phy-X/PSD. We calculated radiation attenuation parameters for the selected samples for a broad range of energies (0.015–15 MeV), including linear attenuation, the mean free path, the half-value layer, and total atomic and electronic cross-sections. The effective atomic number and the effective conductivity were also analyzed to investigate the radiation attenuation features. Also, the analyzed samples' buildup factors were studied. The samples' parameters were compared to materials frequently used to shield against radiation, including ferrite, chromite, barite, magnetite, and RS (253 G18, 360, 520) glass. Due to MFP and HVL values, Ag 2 S has better attenuation features than all the other samples utilized in the comparison. Fast neutron removal cross-sections (FNRCS) were also studied, and the best neutron attenuation composite among the samples under study, according to the FNRCS data, is Ag 2 S (0.116 cm−1). [ABSTRACT FROM AUTHOR]

Most techniques that are used for transmission imaging with ionizing radiation use X-rays, which have the advantage of providing quick, high-resolution images with a relatively small dose of radiation. However, they also have the disadvantage that their penetrating power can be limited in some forms of matter. This can make the discrimination of materials with a low atomic number particularly challenging. Of specific interest in this regard is the need to screen a diversity of manmade items that are heterogeneous and with the tendency to have many interfaces between components that can comprise a diversity of low-mass elements and compounds. These items usually have a compact geometry and a high density of components, which can make them less easy to be imaged quickly and effectively with X-rays. This limit of current screening technology necessitates further stages of examination reducing the ease with which this is done for manufacturing and quality assurance applications. The results presented in this paper demonstrate that, either via fast-neutron radiography or tomography, the potential exists to discern a variety of low-A compounds from one another. Via Monte Carlo simulations, it will be shown that fast-neutron radiography undertaken with a portable, isotopic radiation source (californium-252), absorption and scattering by the doped polymeric materials yields a degree of distinction from other substances. Considering these results, the state-of-the-art of the technique leading to the realization of a combined, real-time fast-neutron and γ -ray radiography system will also be presented, as well as the first experimental results. • This paper presents the potential of a real-time fast neutron and γ -ray imaging technique. • The technique would be suitable for the characterization of low-mass, solid-phase media. • Lithium Ion polymer can be discerned from some hazardous materials under neutron radiography. [ABSTRACT FROM AUTHOR]

The current paper addresses the influence of Rb 2 O in the lithium-borotellurite (LBT) glass system for the first time. For this, the glass system (25-x)Li 2 O–15B 2 O 3 –60TeO 2 -xRb 2 O was designed where x: 0, 5, 10, 15, 20, and 25 mol %. An extensive investigation was carried out to understand the alterations in physical, optical, thermal, and mechanical properties with the use of theoretical calculations. The user-friendly Phy-X/PSD software was employed to demonstrate the nuclear radiation protection properties. From physical property calculations, the addition of Rb 2 O from 0 to 25 mol% increased average molecular weight (AMW) from 113.68 to 152.94 g mol−1 and glass density (ρ glass) from 4.2743 to 4.7710 g cm−3. Likewise, molar volume (V m), oxygen molar volume (V O), oxygen packing density (OPD), and number of bonds per unit volume (n b) were considerably changed by the increasing Rb 2 O concentration. According to the optical calculations, the refractive index (n) increased from 2.3348 to 2.6104, while the dielectric constant (ε) increased from 5.45 to 6.81. Moreover, the metallization criterion (M) showed a decreasing trend, and implied increasing insulation with the increase in Rb 2 O in the glass system. For thermal property estimations, viscosity versus temperature profiles clearly indicated that all R-series have the ability to form glass, but decreasing the Li 2 O caused an increment in glass melting temperature. The mechanical moduli determinations via the Mackenzi-Makishima model demonstrated that Young's (E), bulk (B), shear (S), and longitudinal (L) moduli were gradually decreased by introducing Rb 2 O into the glass network. From the perspective of radiation shielding calculations, the essential parameter, linear attenuation coefficient (LAC), effectively improved by increasing the doping rate of Rb 2 O. Based upon the LAC values, the other critical parameters such as mean free path (MFP), half-value layer (HVL), and effective atomic number (Z eff) were successfully evaluated. Additionally, build-up factors such as exposure (EBF) and energy absorption (EABF) were assessed with the implementation of G-P progression. They showed that sample-R25 ensured better gamma-ray shielding properties compared to the other samples. Lastly, fast neutron removal cross-section (FNRCS) determinations displayed decreasing behaviour with the increasing Rb 2 O content, which is not convenient for effective neutron shielding abilities. All in all, the Rb 2 O-reinforced borotellurite glass can serve as an alternative radiation shielding material. • The first Rb 2 O-added Li 2 O–B 2 O 3 –TeO 2 glass was evaluated. • The ρ glass increased from 4.2743 to 4.7710 g cm−3 for R0 to R25 series, respectively. • The highest LAC values for the sample-R25 were clearly reported in all photon energies. • The lowest HVL is achievable for R25 as 1.84 cm at 0.662 MeV. • EBF and EABF indicated that sample-R25 ensured better gamma-rays shielding properties. [ABSTRACT FROM AUTHOR]

In this paper, four samples of bismuth barium telluroborate glasses in the chemical composition of 20Bi 2 O 3 + 30BaO + xEr 2 O 3 + (30 – x)B 2 O 3 + 20TeO 2 , here x is between 0.05 and 2 mol%) coded as BTBE1, BTBE2, BTBE3, and BTBE4 are reported for potential use in nuclear shielding applications. Geant4 simulations were well designed to obtain the mass attenuation coefficient, μ/ρ for the BTBE1 – BTBE4 specimens at 356 keV–2.51 MeV photon energies. Then, the obtained results are confirmed by using WinXCOM platform. The μ/ρ values were used to assess the nuclear shielding capacity of BTBE1 – BTBE4 specimens in terms of effective atomic number, Z eff , mean free path, MFP, and half-value layer, HVL. Additionally, the buildup factors of BTBE1 – BTBE4 specimens were computed via G-P fitting method at 0.015–15 MeV photon energies and up to 40 mfp (penetration depths). Also, the neutron shielding capacity of the glasses was assessed by calculating the removal cross sections (∑ R). Our results indicate that there is a remarkable enhancement in the gamma shielding features by adding Er 2 O 3 content in the BTBE1 – BTBE4 specimens. It is found that BTBE4 and BTBE3 glass specimens have high shielding quality against nuclear radiation. Gamma-rays and fast neutrons shielding parameters of the BTBE1 – BTBE4 specimens are compared with several commercial and traditional shielding materials. These comparisons concluded that the reported glasses are quite useful for radiation protection purposes. Variation of HVL of BTBE1, BTBE2, BTBE3 and BTBE4 glasses with chemical composition along with comparison to other glasses containing PbO (solid lines) at 662 keV for Te5 glass and at 1173 keV for Ge5 glass. [Display omitted] • Bismuth barium telluroborate glasses doped with Er2O3 were reported. • Good agreement between Geant4 simulation and theoretical calculations. • The maximum HVL was observed at 2.51 MeV. • BTBE4 glass is recommended for radiation protection applications. [ABSTRACT FROM AUTHOR]