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{sup 125}I Measurements for Occupational Exposure Assessment

Journal Article · · AIP Conference Proceedings
DOI:https://doi.org/10.1063/1.2979078· OSTI ID:21152371
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  1. Department of Radiological Protection and Nuclear Safety, ITN-Nuclear and Technological Institute, Estrada Nacional N 10, 2686-953 Sacavem (Portugal)
Whenever there is a risk of occupational exposure to dispersible radioactive material, it is necessary to have a monitoring program to assess the effective dose arising from the intake of radionuclides by workers. In this paper we present our experience in bioassay measurements of {sup 125}I in urine samples of workers using high resolution gamma spectrometry. For a 24-hour excretion period, we found activity values of the order of one Bq and estimated the committed effective doses to be less than one {mu}Sv. Although very small, these values led to a re-evaluation and improvement of the laboratory safety conditions. We discuss the calibration procedure followed for the activity measurements, the estimation of the uncertainty in the excreted activity, the calculation of detection and quantification limits and estimation of performance indicators. Aspects regarding the spectral analysis, true coincidence summing and matrix effects are also considered.
OSTI ID:
21152371
Journal Information:
AIP Conference Proceedings, Journal Name: AIP Conference Proceedings Journal Issue: 1 Vol. 1036; ISSN APCPCS; ISSN 0094-243X
Country of Publication:
United States
Language:
English