Abstract
At radioactive waste disposal facilities all around the world, radiation shielding is required to reduce the background γ-radiation as much as possible in order to achieve protection against high radiation. In the current study, an inexpensive material, Portland cement, has been utilized as shielding material against γ-radiation from radioactive materials including radioactive wastes. Portland cement was used as principal compound and mixed with various ratios of bitumen (0, 10, 20, 30%). Three parameters (compressive strength, permeability and attenuation coefficient) were monitored to estimate the mechanical, physical stability and isolation performance of cement-bitumen as novel γ-radiation shielding material. These parameters were studied under several variable conditions, and results were supported by spectroscopic and scanning investigations. The results confirmed that the cement-bitumen composite (with 10% bitumen) has a high attenuation coefficient comated to the measured for the pure cement paste. Although the compressive strength has decreased gradually with increasing the amount of bitumen relative to cement, the porosity and water absorption capacity have increased gradually at higher bitumen ratio, and consequently the shielding performance outperformed the control sample. As major outcome, this novel composite material could be safely applied in encapsulating or disposing hazardous nuclear waste generated by non-military applications (nuclear power plants) for efficient shielding of the environment from precarious γ-radiation.
Published Version
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