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Handling the 252Cf radionuclide source poses a potential hazard of skin surface contamination in case of an unexpected occurrence. Consequently, there is a growing need to establish precise dose conversion coefficients tailored to each type of emitted primary particle and various radionuclides. Nevertheless, the current body of literature does not provide specific data or methodologies for evaluating skin contamination dose and its associated coefficients, particularly with regard to the 252Cf source. Thus, this study aims to quantify the dose rate received by the skin and its associated coefficients after contamination scenario. Utilizing the established MCNPX environment, the Equivalent dose rate and Absorbed dose, along with Skin contamination dose coefficient (SCDC), have been calculated within the skin tissue. Two methodologies, specifically Watt Fission distribution and the Doppler Effect, are proposed to analyze particle spectra within skin phantom, enabling the calculation of Equivalent dose rate. In accordance with ICRP recommendations regarding the optimal depth for assessing skin doses, the designated scoring volume within the skin is located between depths of 50–100 μm. This volume is tasked with evaluating the dose. The SCDC results were entirely consistent with previously published data from MCNPX, with statistical uncertainties of less than 15%, demonstrating the efficacy of the methodologies employed in this study. This research presents an innovative method for generating data related to skin contamination doses. The novel outcomes in the current research facilitate the assessment of skin dose contamination for the targeted radionuclides and radiotherapy purposes due to staff oversight and radiobiological effects. • The rise in D associated with neutron particles should be managed due to their high RBE. • The SCDC for neutron particles demonstrate a consistent pattern followed by a notable increase. • The SCD measures approximately 4.04 for neutrons and 3.77 × 10 −1 for gamma photons. [ABSTRACT FROM AUTHOR]

This study explores the physical, elastic, and radiation shielding properties of SrO–B 2 O 3 -based bioactive glass systems. The interest in BAG has grown significantly in recent years due to their applications in biomedicine, including bone transplants, wound care, and dental treatments. Borate-based glass matrices have emerged as a promising alternative to silicate-based BAG, exhibiting faster conversion to hydroxyapatite (HA) in physiological fluids and promoting cell proliferation for bone healing. The procedure known as melt quenching is used to prepare the glasses. The effects of varying SrO content on the glass properties were evaluated to understand their potential applications in the field of radiation shielding. Experimental results were compared with theoretical models, including the Makishima, Mackenzie, and Rocherulle models, to determine the most appropriate model for analyzing the elastic properties. The Rocherulle model was found to be in better agreement with experimental results. It was observed that the elastic modulus increased with increasing SrO content, suggesting improved mechanical strength due to higher cross-link density in the glass network. Furthermore, the glasses exhibited low Poisson's ratio values, indicating increased resistance to deformation under stress. The Phy-X program was used to determine the mass attenuation coefficient (G MAC), which is the fundamental parameter for evaluating the interaction of radiation with shielding materials. The G MAC results increase as the amount of SrO is increased from 0 to 6 wt%. In addition, the findings demonstrated that the effective atomic number (Z eff) of the produced glasses rise when the amount of SrO is increased from 0 to 6 wt%. The comprehensive analysis of physical, elastic, and radiation shielding properties provides valuable insights into the optimization of glass systems for specific applications in industries that require mechanical strength and radiation protection. • Gamma-ray properties for glass samples have been studied using Monte Carlo method. • Mechanical properties for xPbO–RNa 2 B 4 O 7 –(100-R-x)[CaO–Al 2 O 3 –SiO 2 ] have been measured. • 50PbO–50Na 2 B 4 O 7 –(100-R-x)[CaO–Al 2 O 3 –SiO 2 ] glass sample is the superior gamma-ray shielding. [ABSTRACT FROM AUTHOR]

In this study, we explore the interactions of photons, protons, and alpha with matter in the context of two drugs, MDPLu and EDTMPLu, delving into the interesting field of radiation shielding. Our research is focused on the mass attenuation coefficient (G MAC), effective atomic number (Z eff), buildup factors (EBF and EABF), and dosimetry parameters with the goal of understanding how these factors affect how well these drugs work as radiation shields. Our results show that the effective atomic number was higher in substances with a higher percentage of Z element component, and that the G MAC values for MDPLu medications were the highest, while the G MAC values for EDTMPLu medications were the lowest. Additionally, MDPLu showed the lowest exposure buildup factor (EBF) and energy absorption buildup factor (EABF), further validating its efficacy as a shielding material. Moreover, MDPLu displayed a higher mass-stopping power (MSP) for proton interactions in the lower energy range, making it a prime candidate for specific radiation shielding applications. These insights contribute to our understanding of the radiation-shielding efficacy of bone cancer treatment medications. • Radiation interactions properties of medications used for some bone cancers were investigated. • Radiation and medications interactions were investigated such as G MAC , Z eff , MSP, and G RDD. • The ordering of the radiation interaction probability was observed as MDPLu > EDTMPLu at the energy range studied. [ABSTRACT FROM AUTHOR]

Abstract Poly vinyl alcohol (PVA) mixed with varying degrees of Pb(NO 3) 2 (0–30 wt%) as reinforced materials were prepared in this paper. The construction and optical properties of samples have been studied using Fourier-transform infrared (FTIR) at 400-4000 cm−1 UV-VIS at 190–900 nm. Gamma-ray shielding properties were analyzed by 133 Ba (0.356 MeV) and 137 Cs (0.662 MeV) gamma ray source, Xcom program and MCNP5 code. The results showed that shielding properties of polyvinyl alcohol increased by the increment of lead nitrate. The experimental values were in good agreement with the Xcom values and MCNP5 code, thus the Xcom and MCNP5 could be used to analyze the shielding performance accurately. Moreover, exposure buildup factor (EBF) and energy absorption buildup factor (EABF) of shielding materials were analyzed by G-P fitting method at 0.015–15MeV. Graphical abstract Image 1 Highlights • PVA mixed with varied degrees of Pb(NO 3) 2 (0–30 wt %) as reinforced materials are prepared. • Gamma ray shielding properties of shielding materials have been measured with 133Ba and 137Cs gamma sources. • The experimental values were mostly in good accord with the XCom values and MCNP5 code. • EBF and EABF at 0.015–15 MeV of samples are calculated. • Construction and optical properties of samples have been studied using FTIR and UV-VIS. [ABSTRACT FROM AUTHOR]

Novel Glass system with a formula of xBaO.(30− x).Na 2 O.70B 2 O 3 (0 ≤x ≤ 30 mol%) have been prepared and examined. The BNaBa x -glass structure was used to estimate the influence of BaO addition on the density and molar volume. There is a linear increase in density with increasing BaO concentration. The molar volume varies oppositely. Furthermore, the impact of barium oxide on the gamma and neutron radiation shielding capacities of xBaO.(30− x).Na 2 O–70B 2 O 3 glasses have been investigated for radiation shielding applications. The μm: coefficient of mass attenuation for BNaBa-0, BNaBa-5, BNaBa-10, BNaBa-15, BNaBa-20, BNaBa-25, and BNaBa-30 glass samples were simulated using the Monte Carlo simulation FLUKA algorithm, in photon energy ranged 0.015MeV–15MeV, the resulting μ m simulated results were compared with the Phy-X/PSD platform. The T 1/2 : half-value layer, λ: mean free path, Z eff : effective atomic number, EBF: exposure, and EABF: energy absorption buildup factors of the BNaBa x -glass samples have been estimated. The results presented that a BNaBa-30-glass with a 30-mol.% concentration of BaO has the best gamma and neutron shielding capabilities than the other investigated BNaBa x -glass samples. • Gamma and neutron shielding properties of BaO–Na 2 O–B 2 O 3 have been studied. • The results were simulated at 0.015–15 MeV and compared with Phy-X/PSD values. • The BNaBa-30 has the best effectiveness shielding against gamma photons. • The results are useful in radiation protection of applications. [ABSTRACT FROM AUTHOR]

In this study, WO 3 based glass system in composition (100- x )[0.1B 2 O 3 -0.4P 2 O 5 -0.5PbO]- x WO 3 where x = 10, 20, 30, 40, 50 and 60 mol% were prepared for gamma ray shielding properties. The emitted gamma ray has been detected by 3 × 3 inch NaI (Tl) scintillation detector. The obtained results indicate that the values of the mass attenuation coefficient (μ m ), effective atomic number (Z eff ) and electron density (N el ) of the glass samples increase with the increasing of WO 3 . The values of the Poisson's ratio (σ), half value layer (HVL) and Mean free path (MFP) of the investigated glasses were found to decrease with the increasing of WO 3 concentration. The μ m results have been observed a perfect agreement with the XCOM values for all the glass samples. [ABSTRACT FROM AUTHOR]

For a PbO–Sb 2 O 3 –B 2 O 3 –CuO glass system, optical, gamma and neutron shielding properties have been comprehensively examined. The absorbance of the recent glasses positively correlated to the increase in PbO content. Our results show that both the band gap and refractive index remain nearly unchanged with PbO content. Adopting NISTXCOM within an energy photon range of 0.015–15 MeV, the shielding parameters were evaluated for glass samples. The results from MAC outline good compliance with the obtained values using FLUKA codes and Phy-X/PSD. Comparatively higher density (4.81 g/cm3), greater shielding parameters values were all achieved for 35PbO–5Sb 2 O 3 –60B 2 O 3 -0.5CuO (PSBC5). 31.2, 35.6, 44.9, 55.1, and 66.3 cm2/g values are the mass attenuation coefficient of PS PSBC1, PSBC2, PSBC3, PSBC4, and PSBC5 glasses at 0.015 MeV. This indicating that PSBC5 sample is the superior gamma shield. In addition, the calculated effective removal cross-sections for fast neutrons observe that the PSBC5sample has commensurately greater Σ R (=0.113 cm−1). Image 1 • Characterization by UV–Vis and density analyses. • XCOM software and the FLUKA Monte Carlo simulation code are utilized to investigate the absorption value. • The plot showed that by increasing the PbO percentage, the shielding parameters increase. [ABSTRACT FROM AUTHOR]

The mechanical behavior and gamma radiation attenuation features of borosilicate glasses with chemical compositions 16ZnO–8BaO-5.5SiO 2 -0.5Sb 2 O 3 -(70-x)B 2 O 3 /xBi 2 O 3 are extensively investigated. Makishima-Mackenzie principle, Monte Carlo code, and Phy-X/PSD software are utilized in terms of determining these properties. Our results showed that the total packing density (V t) decreased from 0.634851 to 0.571458, while the total dissociation energy increased from 26.612 (kJ/cm3) to 29.652 (kJ/cm3) for S1-glass (with 10 mol% of Bi 2 O 3) and S5-glass (with 30 mol% Bi 2 O 3). All elastic moduli are enhanced by increasing the Bi 2 O 3 additive in the investigated glasses. Poisson's ratio was decreased from 0.281226 for S1-glass to 0.256957 for S5-glass. In terms of gamma-ray shielding parameters; linear (μ) and mass attenuation (μ m) coefficients for the rich glass sample with B 2 O 3 (S5) possess the highest values among all investigated (S1–S5) samples. The glass sample S5 is reported with the lowest values of tenth (TVL) and half (HVL) value layers among all studied glasses. In addition, the exposure (EBF) and energy absorption (EABF) bulidup factors were decreased with increasing the amount of Bi 2 O 3 reinforcement for mean free path values from 0.5 to 40 mfp. The lowest possible levels of attenuation (minimum transmission) were measured at a thickness of 3 cm for all of the glass samples. • The mechanical behavior of borosilicate is intensively investigated. • Makishima-Mackenzie principle, and Monte Carlo code are utilized in terms of determining these properties. • Characterization of nuclear radiation shielding properties performed in-silico methods. • Obtained remarkably interesting results on B 2 O 3 –ZnO–BaO–SiO 2 –Sb 2 O 3 –Bi 2 O 3 glasses. • All the obtained results have been linked to their monotonical attitudes. [ABSTRACT FROM AUTHOR]