This study is concerned with the use of the concrete samples produced by tincal concentrator waste as a gamma radiation shield. The values of mass attenuation coefficients for concrete samples measured at 59.54 (Am-241) and 80.99 (Ba-133) keV photon energies. Gamma rays were counted by a NaI(Tl) detector coupled to multi channel analyzer (MCA) using narrow beam transmission arrangement. Theoretical values of mass attenuation coefficients were obtained by using WinXCom computer program and compared with the experimental results. The study reveals that the concrete samples under investigation are more effective than ordinary concrete in small rates for the attenuation of gamma rays.
Key words: Tincal concentrator waste, NaI(Tl), WinXCom.
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