Estimation of the uncertainty in internal dose calculation for two contamination cases

The assessment of internal dose is subject to a large uncertainty due to the limits of measuring technique and to the assumptions made by the expert. Here, we propose an approach to report the confidence interval associated with the evaluated dose. The sources of uncertainties considered so far incl...

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Bibliographic Details
Published in:Radiation protection dosimetry 2007-01, Vol.125 (1-4), p.548-552
Main Authors: Blanchardon, E., Molokanov, A., Franck, D., Kochetkov, O., Panfilov, A., Jourdain, J.-R.
Format: Article
Language:English
Subjects:
Algorithms
Biological Assay - methods
Computer Simulation
Environmental Exposure - analysis
Humans
Internationality
Models, Biological
Radiation Dosage
Radiation Monitoring - methods
Radiation Protection - methods
Radioisotopes - analysis
Radioisotopes - pharmacokinetics
Reproducibility of Results
Sensitivity and Specificity
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Summary:The assessment of internal dose is subject to a large uncertainty due to the limits of measuring technique and to the assumptions made by the expert. Here, we propose an approach to report the confidence interval associated with the evaluated dose. The sources of uncertainties considered so far include the date of intake, the physico-chemical characteristics of the radioactive material, the counting error and the stochastic variability of excretion. Three successive levels of approximation are suggested, depending on the expected dose, for which increasingly realistic parameter values should be sought and applied. Finally, the results of a Monte Carlo dose calculation are presented in the form of a statistical distribution of possible dose values. This approach has been applied to two cases of uranium and caesium exposure.
ISSN:0144-8420
1742-3406
DOI:10.1093/rpd/ncl552