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Materials shielding properties measurement
Michal, Martin ; Burian, Jiří (referee) ; Katovský, Karel (advisor)
This thesis deals with the issue of ionizing radiation, specifically gamma radiation and its shielding. This radiation is produced, for example, during a fission reaction in a nuclear reactor. Materials such as lead, or concrete are most often used to shield gamma radiation. This is due to their low cost and high density. The task of new trends is to try to replace these existing materials with more efficient, lighter, and non-toxic materials. The aim of the practical part was the calculation of linear attenuation coefficients. For the calculation, the values of the thickness of the shielding sheets, the intensity of the unattenuated beam and the attenuated beam were needed. These values were determined from measurements. For more accurate calculations, the background value was also measured, which was then subtracted from the intensity values of the undamped beam. The resulting values were compared with each other.
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