C. Oliveira et al., DENSITY AND WATER-CONTENT CORRECTIONS IN THE GAMMA-COUNT RATE OF A PGNAA SYSTEM FOR CEMENT RAW-MATERIAL ANALYSIS USING THE MCNP CODE, Applied radiation and isotopes, 49(8), 1998, pp. 923-930
Citations number
2
Categorie Soggetti
Nuclear Sciences & Tecnology","Radiology,Nuclear Medicine & Medical Imaging","Chemistry Inorganic & Nuclear
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 de
tector banks were used: a lower bank positioned symmetrically around t
he source to detect gamma-rays emitted downwards; an upper bank detect
s 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. (C) 1998 Elsevier Sci
ence Ltd. All rights reserved.