Density and water content corrections in the gamma count rate of a PGNAA system for cement raw material analysis using the MCNP Code

A MCNP simulation study for a prompt gamma neutron activation analysis system for on-line characterisation of cement raw materials has been carried out. A neutron source is located below a conveyor belt. Two detector banks were used: a lower bank positioned symmetrically around the source to detect γ-rays emitted downwards; an upper bank detects the radiation emitted upwards. The count rate of both detector banks for a given composition depends on the bulk density and water content. This paper reports a few corrections which linearise the dependence of the corrected count rate on the mass content.