Application of new imaging and calculation techniques to activity and dose assessment in the case of a 106Ru contaminated wound

Abstract

The aim of this paper is to describe the dosimetric evaluation of a point contamination that occurred in a laboratory during the examination of an irradiated sample. The incident led to point contamination of the operator's finger due to the presence of mainly 106Ru, with its progeny, 106Rh. The paper reports on the activity and dose assessment, performed using several methods. The measured activity was obtained using a conventional device based on a germanium detector and confirmed using software developed at IRSN, based on reconstruction of voxel phantom associated with the Monte Carlo N-Particle code (MCNP) for in vivo measurement. Two dose assessment calculations were performed using both analytical and Monte Carlo methods, applying the same approach as for activity assessment based on the personal computational phantom of the finger. The results are compared, followed by a discussion on the suitability of the tools described in this study.

Application of voxel phantoms to study the influence of the heterogeneous distribution of actinides in lungs on in vivo counting using animal experiments

“…OEDIPE is based on a Graphical User Interface developed under the IDL environment (Franck et al, 2001;Borisov et al, 2002Borisov et al, , 2005de Carlan, 2004;Aubineau-Laniece et al, 2005a, 2005bPierrat et al, 2005;de Carlan et al, 2005). The software's main goals are the fast creation of voxel phantoms and the automatic writing of the input file for the Monte Carlo calculation code used to simulate particle transport through the matter (MCNP or MCNPX, Hughes et al, 1997;Briesmeister, 2000).…”

“…Then a friendly Graphical User Interface was developed using person-specific computational phantoms in association with the MCNP calculation code. This interface called OEDIPE (French acronym for "tool for personalized internal dose assessment") allows in vivo measurement to be simulated for an improved calibration (Franck et al, 2001;Borisov et al, 2002Borisov et al, , 2005de Carlan, 2004;Aubineau-Laniece et al, 2005a, 2005b.…”

Évaluation de la dose locale pour une blessure contaminée

“…Prendre un ordre de grandeur sur une échelle logarithmique, soit environ un facteur trois de part et d'autre de la valeur calculée, est une estimation réaliste de l'enveloppe de cette incertitude. Des travaux plus fins, mettant en oeuvre des techniques de simulation sur fantôme numérique, sont actuellement menés sur la dosimétrie locale d'une blessure (De Carlan et al, 2003). Il est intéressant de noter que les isodoses tracées dans cette dernière publication à propos du ruthénium 106 (gradient de 50 mSv kBq-' h-' à 0,l mSv kBq-l h-') sont en moyenne tout à fait cohérentes avec la valeur indicative de 1,6 mSv kBq-' h-] donnée dans le tableau 1.…”

Development of Accurate Radioactivity Assessment System for Radiation Survey with Various Detectors

“…In recent years, this technique has been well validated, and has proved to be a useful tool for realistic calibration that is difficult to be achieved with a physical phantom [5][6][7] . However, there still are few practical tools 8) for implementing numerical calibrations, especially for the contamination focused on in the present study, despite an urgent need for such calibration at the sites of radiation emergency medicine.…”