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Development and Validation of an Internal Dosimetric Analyser to Assist Confirmatory, Routine and Special Radiobioassay

Not scheduled
1h 30m
Geneva

Geneva

International Conference Centre Geneva, Switzerland
Poster 3. Monitoring and dose assessment of occupational radiation exposures Session 2. Monitoring and dose assessment of occupational radiation exposures

Speaker

Dr Michael Hajek (International Atomic Energy Agency)

Description

The IAEA Radiation Safety Technical Services Laboratory has developed an Internal Dosimetric Analyser (IDA) software tool to facilitate the access to dosimetric data and perform calculations related to individual monitoring for intakes of radionuclides and occupational radiation protection. Direct (or in-vivo) and indirect (or in-vitro) radiobioassay methods have been developed to detect radionuclides of interest in tissues or organs of the human body or in excreta. IDA serves to correlate measurement data from confirmatory, routine and special internal monitoring with data obtained from the Occupational Intakes of Radionuclides (OIR) series of recommendations published by the International Commission on Radiological Protection (ICRP) [1−4]. The software tool was designed with an intuitive user interface using Microsoft Excel and was written using the programming language Visual Basic for Applications (VBA). The objective of IDA is to keep the internal dosimetry data in the background and allow the dosimetrist to make the necessary calculations so as to be able to decide, given the bioassay method and monitoring period: (i) whether the method and period are appropriate for confirmatory or routine monitoring; (ii) whether the method and monitoring period allow the recording level to be detected; (iii) whether previous intakes are interfering with the current measurement; and (iv) how uncertainties in the measurement affect the dose assessment. IDA can present additional information such as the minimum detectable dose as a function of the time after intake, derived recording levels for radionuclide mixtures, committed effective dose calculations for data from air monitoring and the ISO 27048 procedure for the assessment of doses based on bioassay measurements [5]. Isodose curves are shown that allow a quick estimate of the committed effective dose when the time of the intake is known. IDA was successfully validated for functionality according to the requirements of ISO/IEC 17025.

References:

  1. INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION, Occupational Intakes of Radionuclides: Part 1, Publication 130, Elsevier (2015).
  2. INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION, Occupational Intakes of Radionuclides: Part 2, Publication 134, Elsevier (2016).
  3. INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION, Occupational Intakes of Radionuclides: Part 3, Publication 137, Elsevier (2017).
  4. INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION, Occupational Intakes of Radionuclides: Part 4, Publication 141, Elsevier (2019).
  5. INTERNATIONAL ORGANIZATION FOR STANDARDIZATION, Radiation Protection — Dose Assessment for the Monitoring of Workers for Internal Radiation Exposure, ISO 27048:2011, ISO, Geneva (2011).
Speakers email M.Hajek@iaea.org
Speakers affiliation International Atomic Energy Agency
Name of Member State/Organization International Atomic Energy Agency

Author

Dr Michael Hajek (International Atomic Energy Agency)

Co-authors

Dr John Hunt (International Atomic Energy Agency) Mr Antonio Capote-Cuellar (International Atomic Energy Agency) Mr Rodolfo Cruz Suárez (International Atomic Energy Agency) Mr Patrick Kenny (International Atomic Energy Agency) Mr Gabor Lafranco (International Atomic Energy Agency)

Presentation materials