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Radiation Protection Dosimetry 2005 115(1-4):113-116; doi:10.1093/rpd/nci253
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© The Author 2005. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oxfordjournals.org

Non-destructive method of characterisation of radioactive waste containers using gamma spectroscopy and Monte Carlo techniques

D. Ridikas*, S. Feray, M. Cometto and F. Damoy

CEA Saclay, DSM/DAPNIA F-91191 Gif-sur-Yvette, France

* Corresponding author: ridikas{at}cea.fr

During the decommissioning of the SATURNE accelerator at CEA Saclay (France), a number of concrete containers with radioactive materials of low or very low activity had to be characterised before their final storage. In this paper, a non-destructive approach combining gamma ray spectroscopy and Monte Carlo simulations is used in order to characterise massive concrete blocks containing some radioactive waste. The limits and uncertainties of the proposed method are quantified for the source term activity estimates using 137Cs as a tracer element. A series of activity measurements with a few representative waste containers were performed before and after destruction. It has been found that neither was the distribution of radioactive materials homogeneous nor was its density unique, and this became the major source of systematic errors in this study. Nevertheless, we conclude that by combining gamma ray spectroscopy and full scale Monte Carlo simulations one can estimate the source term activity for some tracer elements such as 134Cs, 137Cs, 60Co, etc. The uncertainty of this estimation should not be bigger than a factor of 2–3.


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