DENSITY AND WATER-CONTENT CORRECTIONS IN THE GAMMA-COUNT RATE OF A PGNAA SYSTEM FOR CEMENT RAW-MATERIAL ANALYSIS USING THE MCNP CODE

Citation
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
Journal title
Applied radiation and isotopes
ISSN journal
09698043 → ACNP
Volume
49
Issue
8
Year of publication
1998
Pages
923 - 930
Database
ISI
SICI code
0969-8043(1998)49:8<923:DAWCIT>2.0.ZU;2-C
Abstract
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.