Assessment of X-ray shielding properties of polystyrene incorporated with different nano-sizes of PbO

PbO (lead oxide) particles with different sizes were incorporated into polystyrene (PS) with various weight fractions (0, 10, 15, 25, 35%). These novel PS/PbO nano-composites were produced by roll mill mixing and compressing molding techniques and then investigated for radiation attenuation of X-rays (N-series/ISO 4037) typically used in radiology. Properties of the PbO particles were studied by X-ray diffraction (XRD). Filler dispersion and elemental composition of the prepared nano-composites were characterized using scanning electron microscopy (SEM) and energy-dispersive X-ray spectroscopy (EDS), revealing better filler distribution and fewer agglomerations with smaller PbO particle size. Linear and mass attenuation coefficients (μ and μ_m), total molecular and atomic cross-sections (σ_mol and σ_atm), as well as effective atomic number and electron density (Z_eff and N_eff), were calculated for the energy range N40 to N200. The influence of PbO weight percentage on the enhancement of the shielding parameters of the nano-composites was expected; however, the effect of PbO particle size was surprising. Linear and mass attenuation coefficients for PS/PbO composites increased gradually with increasing PbO concentrations, and composites with a small size of nanoparticles showed best performance. In addition, increasing PbO concentration raised the effective atomic number Z_eff of the composite. Hence, the electron density N_eff increased, which provided a higher total interaction cross-section of X-rays with the composites. Maximum radiation shielding was observed for PS/PbO(B). It is concluded that this material might be used in developping low-cost and lightweight X-ray shielding to be used in radiology.

Effects of some level density models and γ-ray strength functions on production cross-section calculations of 16,18O and 24,26Mg radioisotopes

Oxygen and magnesium isotopes can be used in nuclear reactor materials as cooling, shielding, coating, electronics etc. They can also occur through nuclear reactions during the reactor operation. The exposure of high energy gamma can change the material and its properties, and hence its objective of selection may not remain satisfied. Thus, it is required to study the cross section of different reactions on nuclear reactor materials to understand their sustainability for the properties, for which they are chosen. In the scope of this study, theoretically, different level density model calculations and γ-ray strength functions have been performed for (γ, p) reaction for 16,18O and 24,26Mg nuclei using TALYS 1.9 and EMPI˙RE 3.2.2 codes. Also, semi empirical (γ, p) formula by Tel et al., have been calculated and compared with all results. The effect of different level density models defined in these codes on gamma strength has been studied. Finally, the consistency of these obtained data with EXFOR data have been investigated.

Study on gamma ray shielding performance of concretes doped with natural sepiolite mineral

Gamma ray attenuation coefficients for various concrete types containing natural sepiolite mineral and B4C have been experimentally investigated at different gamma energies. In order to obtain the gamma rays, the four radioactive point-isotropic sources 133Ba, 137Cs, 60Co and 22Na which energies ranged from 80.9 to 1332.5 keV have been utilized. The measurements have been carried out by using HPGe detector and MCA equipped with a personal computer. The morphological structure and elemental compositions of the concretes have been measured with scanning electron microscope (SEM) and energy-dispersive X-ray (EDX) analyses. Linear attenuation coefficient (μ), mass attenuation coefficient (μ m ), half value layer (HVL) and mean free path (MFP) have been calculated for all concretes. The obtained results have been compared to the other materials such as Pb and Al.