Calculation of the gamma radiation shielding efficiency of cement-bitumen portable container using MCNPX code

Faculty Science Year: 2021
Type of Publication: ZU Hosted Pages:
Authors:
Journal: Progress in Nuclear Energy Elsevier Volume: 142
Keywords : Calculation , , gamma radiation shielding efficiency , cement-bitumen    
Abstract:
In the current study, the shielding characteristics of Portland cement combined with various percentages of bitumen (from 10% to 50%) materials were investigated. The MCNPX code was used to calculate the linear and mass attenuation coefficients, half and tenth value layers, and the mean free path for gamma rays. For the calculations, gamma sources ( 137Cs with 0.662 MeV and cobalt 60Co with an average energy of 1.25 MeV) were employed. In comparison to the cement paste solely, the cement-bitumen composites have a greater photon attenuation coefficient. It is suggested that new compositions can be used as shielding material for dual photon protection and would be recommended in casting containers of thickness 6 cm for embedding the cesium ( 137Cs) and cobalt ( 60Co) as a mobile container during transportation and long storage.
   
     
 
       

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