Abstract
Recently, technologists try to develop novel gamma radiation shielding materials instead of traditional materials such as lead and concrete with improved performance in gamma radiation shielding in medical applications and nuclear reactors. For this purpose, alloys such as stainless steel (SS) and carbon steel (CS) attracted much attention, these days. Preliminary results on such alloys have shown better attenuation of γ rays as compared to traditional shielding materials. This work aimed to conduct research on different alloy samples to evaluate their radiation attenuation efficiency and their suitability for radiation shielding when utilized in nuclear facilities. The mass attenuation coefficients for eight alloy samples were measured at different photon energies ranging from 80.997 to 1332.501 keV using transmission geometry. From the mass attenuation coefficients, different photon attenuation parameters such as half value layer, mean free path, effective atomic number, and radiation protection efficiency were evaluated. In addition, the equivalent atomic number and the exposure buildup factor were calculated using G-P fitting method for photon energy ranging from 0.015 MeV to 15 MeV at different penetration depth. The results showed that the Z
values remain almost constant for all samples except W72/Cu28 in which the Z
for this sample tends to decrease with the energy. The lowest value of half value layer is found for the alloy sample Ta97.5/W2.5 and the highest value is found for the alloy sample In50/Sn50. The Ta97.5/W2.5, Ta90/W10, Ta95/W5 samples demonstrated good radiation attenuation properties.