Determination of radiation shielding parameters of 304L stainless steel specimens from welding area for photons of various gamma ray sources

Evaluation of radiation interaction parameters of some shape memory alloys

In this study, effective atomic number (Zeff), atomic (σta) and electronic cross section (σte) values of some shape memory alloys (SMA) were calculated at energies 5.9, 6.1, 8, 11.2, 25, 59.543, 75, 112, 149 keV. It has been observed that the obtained values of the calculated parameters vary depending on the photon intensity, chemical constitution and density of the alloys. Calculations were made using the WinXCom program and the graph of the change according to the energy of the obtained results was drawn. The results of this study are thought to be beneficial in the application of various fields.

Investigation of shielding properties of impregnated activated carbon for gamma-rays

Carbon related structures are extraordinarily attractive materials for researchers and especially for organic chemistry, besides being the most important basic materials of daily life. The richness of various optical and electronic behaviors has made them one of the rapidly rising materials on the horizon of material science and condensed matter physics. Having the sheets of atoms that are stacked in a disorganized manner makes activated carbon being different from other forms of carbon -graphite- structures. The researches about the shielding properties of activated carbon atoms for gamma-rays are very rare and required to be improved. Since the use of radioactive sources in different fields (nuclear industry, shielding material, radiation biophysics and space research application, etc.) has been increasing expeditiously, the photon interactions with matter has gained more importance in the world of material science technology. In this article, we review the basics of the impregnated activated carbons (AC1 and AC2), as well as the link between the structural behaviors and the gamma shielding properties in terms of both quality and efficiency. Both XCom software and EGSnrc simulation code were used to obtain the theoretical calculations that are significantly important to be able to understand the shielding properties of impregnated activated carbons (AC1 and AC2) for gamma-rays. At the end, the mass attenuation coefficients (μ_m), the total atomic and the electronic cross-sections (σ_t,a and σ_t,e), the effective atomic number and the effective electron density (Z_eff and N_eff), the half value layer (HVL), the tenth value layer (TVL), and the mean free path (MFP) values of such materials were calculated and then compared with those of some other known shielding materials like lead, borosilicate, concrete and vermiculite. The calculated data showed that impregnated activated carbons (AC1 and AC2) are very appropriate and consistent to be one of the candidates for shielding materials of gamma-rays.

Investigation of gamma-ray attenuation coefficients for solid boronized 304L stainless steel

In this study, mass attenuation coefficient (μ/ρ) and half value layer (HVL) at Eu-152 and Co-60 energies were used in measuring attenuation coefficients of the solid boronized AISI 304L stainless steel at 950 °C for 2, 4, 6 and 8 h. The experimental mass attenuation coefficients, μ/ρ, and HVL for these materials were compared to theoretical values obtained with WinXCOM. At the same time a new boriding agent (Baybora®-1) also developed for solid boriding method was used. The effects of boron layer size on radiation attenuation of boronized composites were evaluated in relation with gamma-ray transmission and the results of the experiments were interpreted. It could be understood that increased of boron layer in AISI 304L causes of increases in the attenuation coefficient values. The measured values agree with the theoretical values. The interaction parameters for selected samples have been computed and provided in the extended energy range 10^-3-10⁴ MeV. The shielding properties prepared stainless steel have also been compared with standard concretes as well as with the standard shielding stainless steel. It is found that the prepared stainless steel is the better shielding substitute to the conventional concretes as well as other standard shielding stainless steel. So, submicron size boron layer used composite materials are more convenient than micron size boron used composite materials as radiation shielding materials for nuclear applications.

Gamma radiation shielding properties of some Bi-Sn-Zn alloys

We investigate the gamma radiation shielding properties of some Bi-Sn-Zn alloys. For this study, we synthesised five bismuth-based lead-free alloy samples using the melt quench technique with the composition Bi50Sn[Formula: see text]Zn[Formula: see text] where [Formula: see text] Apart from physical parameters such as the weight, density, and thickness of the alloy samples, we estimated their optimum thickness range at photon energies of 122, 511, 662, and 1250 keV. The mass attenuation coefficients and effective atomic number, measured experimentally, were found to be in close agreement with values computed using WinXCom software, within a ± 4% error. From the transmitted photon spectra, the radiation protection efficiency (RPE) was determined and analysed for different alloy compositions. A correlation between RPE and effective atomic number was established at different photon energies. The Bi50Sn50 binary alloy composition is reported to exhibit maximum shielding efficiency.