Open Access
BIO Web Conf.
Volume 14, 2019
The 12th International Conference on the Health Effects of Incorporated Radionuclides (HEIR 2018)
Article Number 03016
Number of page(s) 2
Section Dosimetry and Dose Assessment: Poster presentation
Published online 07 May 2019

The assessment of internal exposure for workers is usually based on ambient activity measured at the workplace or individual activity from bioassay interpreted with dose coefficients and time-dependent retained and excreted fractions of intake established by the International Commission on Radiological Protection (ICRP) from reference biokinetic and dosimetric models.

To gain flexibility in the implemented models and enable consideration of non-standard situations of exposure such as wound contamination, clinical trials of radiopharmaceuticals, exposure to radon decay products with specific aerosol parameters or intake followed by decorporation treatment, a new software module, called “Internal dose CAlculation for Radionuclide Exposure (ICARE)”, was developed for expertise and research. It provides the dose coefficients and retained/excreted fractions used by OPSCI software [1] (IRSN-ORANO) which performs occupational dose calculation from bioassay measurement, evaluates the associated uncertainty and supports design of monitoring programs of internal exposure.

ICARE will be presented as software developed with the Interactive Data Language (IDL, Harris) to implement biokinetic models of the ICRP 60 [2] series of publications by the method described by Leggett et al. [3]. It provides retained fractions of intake in body regions, daily urinary and fecal excretions after occupational exposure by inhalation, ingestion or wound [4]. S coefficient values are calculated from emission spectra of ICRP [5] convoluted with specific absorbed fractions published by Cristy and Eckerman [6] for photons and by ICRP [7, 8] for electrons and alpha particles. S coefficients are combined with numbers of nuclear transformations to provide absorbed, equivalent and effective doses per unit intake.

For validation, calculation results were extensively compared with ICRP equivalent and effective dose coefficients [9] and with bioassay quantities predicted by DCAL [10] and IMBA [11] software. Examples for specific exposure situations will be presented. Further development is planned to include age-dependent models and revised ICRP models implemented in the Occupational Intakes of Radionuclides series of publications [12] with the objective of contributing to the quality assurance of the on-going update of ICRP dose coefficients for internal exposure.


© The Authors, published by EDP Sciences, 2019

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