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Radiation Protection Dosimetry Advance Access originally published online on May 26, 2007
Radiation Protection Dosimetry 2008 128(1):49-61; doi:10.1093/rpd/ncm242
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© The Author 2007. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oxfordjournals.org

Monte Carlo calculations applied to the parametrical studies in a whole body counter

Jean Louis Genicot1,*, Virginia Koukouliou2 and Eleftheria Carinou2

1 Belgian Nuclear Research Centre—SCK-CEN, Division of Radiation Protection, Department of Safeguard and Nuclear Measurements, Boeretang 200, B-2400 Mol, Belgium
2 Greek Atomic Energy Commission, Department of Environmental Radioactivity, Ministry of Development, Attiki, PO Box 60092, 11310 Agia Paraskevi, Athens, Greece

* Corresponding author: jgenicot{at}sckcen.be

Received January 25, 2007, amended March 17, 2007, accepted April 18, 2007

The use of a Monte Carlo code for the analysis and interpretation of whole body counting measurements is described. The sources of error are analysed and commented to show how a counting geometry can be improved by improving accuracy and precision in a measurement. The effects of body size, contamination distribution and counting geometry are also parameters which can be easily used to improve the quality of a body burden assessment. The optimisation of the detector (position, shielding, shape and size) is also commented on the basis of calculations in the photon energy range usually encountered in routine measurements. The results obtained from these simulations are confirmed by experimental results.


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