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

Sonia M. Reda, Hosam M. Saleh

2021Progress in Nuclear Energy45 citationsDOI

Topics & Concepts

Electromagnetic shieldingMaterials scienceAttenuationCementGamma rayAsphaltNuclear engineeringMass attenuation coefficientRadiation shieldingPortland cementAttenuation coefficientHalf-value layerComposite materialNuclear physicsOpticsPhysicsEngineeringRadiation Shielding Materials AnalysisGraphite, nuclear technology, radiation studiesRadioactivity and Radon Measurements
Calculation of the gamma radiation shielding efficiency of cement-bitumen portable container using MCNPX code | Litcius