IRSN, Institut de radioprotection et de sûreté nucléaire

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Enhancing Nuclear Safety



An european project : OMINEX Optimisation of Monitoring for Internal Exposure

European IRPA congress, Florence, 8-11 October 2002 B. Le Guen (1), E. Ansoborlo (2), P. Bérard (3), C. Cossonnet (4), D. Franck (4), J.L. Genicot (5), C. Hurtgen (5), J.R. Jourdain (4), M.L. Perrin (4), T. Rahola (6), R. Sundell (7), J. Sovijärvi (7), G.N. Stradling (8) and G. Etherington (coordinator) (8) (1) Electricité de France (EDF-GDF), SCAST, Immeuble Becquerel, 6 rue Ampère. F-93203 Saint-Denis, France (2) Commissariat à l’Energie Atomique (CEA), CETAMA, Marcoule, France (3) Commissariat à l’Energie Atomique (CEA), Unités de Gestion, Sécurité, Protection, LABM, bâtiment 601 CEA Saclay F-91191 Gif sur Yvette cedex, France (4) Institut de Radioprotection et de Sûreté Nucléaire, IRSN/DPHD, BP 17, 92265 Fontenay-aux-Roses cedex, France (5) Belgian Nuclear Research Center (SCK.CEN), Boeretang 200- B-2400 Mol, Belgium (6) STUK – Radiation and Nuclear Safety Authority, P.O. Box 14. FIN-00881 Helsinki, Finland (7) TVO Nuclear Services Ltd (TVONS) FIN-27160 Olkiluoto Finland (8) National Radiological Protection Board (NRPB), Chilton, Didcot, Oxon. OX11 ORQ, United Kingdom


This project aims to develop practical methods that could be used to optimise the design and implementation of internal exposure monitoring programmes for specified exposure situations (eg a particular radionuclide, industrial process, and/or installation). It will be important to address practical monitoring requirements, rather than idealized situations. The outcome of the project should be a common approach to the design and implementation of internal dose monitoring programmes throughout the EU. Optimisation will involve consideration of overall design of a monitoring programme, choice of measurement (air concentration, body activity, excretion rates), choice of monitoring techniques (including new techniques, for instance mass spectrometry for bioassay), monitoring intervals, measurement frequency, measurement sensitivity, and measurement precision. To assess the current position in the EU, a survey of internal dose monitoring programmes currently in use is being carried out. Information is also being collected on the financial costs of implementing and running such programmes. The “benefit” of a particular monitoring programme will be quantified primarily by assessing the accuracy with which intakes and/or committed doses are determined. Therefore, the major sources of uncertainty in assessed internal dose are being investigated and quantified ; this involves consideration of monitoring programme design, measurement uncertainties, data analysis, intake modelling, biokinetic modelling, model parameter selection and evaluation of dose coefficients. Methods for optimisation of monitoring will be developed by considering a range of practical examples of acute and non-continuous chronic exposures to industrial materials (eg exposure to : uranium oxide mixtures during fuel fabrication ; plutonium nitrate during reprocessing). Guidance on monitoring will be developed for the specific examples. This guidance will be generalised to give generic advice on the design and implementation of internal dose monitoring programmes. Finally, a training course will be organised close tot the end of the project to disseminate the findings to radiation protection professionals, regulators and senior medical staff.


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