Internal dosimetric analyser to assist routine, confirmatory and special radiobioassays.

The IAEA Radiation Safety Technical Services Laboratory has developed and validated an Internal Dosimetric Analyser (IDA) software tool to facilitate access to dosimetric data and perform calculations related to individual monitoring for intakes of radionuclides and occupational radiation protection. IDA serves to correlate measurements from routine, confirmatory and special internal monitoring with data obtained from the Occupational Intakes of Radionuclides series of recommendations published by the International Commission on Radiological Protection. The purpose of IDA is to keep the internal dosimetry data in the background and allow the dosimetrist to make the necessary calculations to be able to decide (1) whether the bioassay method and monitoring period are appropriate for routine, confirmatory or special monitoring; (2) whether the method and period will allow the recording level to be detected; (3) whether previous intakes are contributing to the current measurement; and (4) whether measurement uncertainties affect the dose assessment.

Reconstructive dosimetry and radiation dose evaluation of workers and public due to a Brazilian radiological accident in industrial radiography.

Radiological accidents occur mainly in the practices recognized as high risk and which are classified by the International Atomic Energy Agency (IAEA) as Categories 1 and 2: radiotherapy, industrial irradiators and industrial radiography. In Brazil, five important cases in industrial gamma radiography occurred from 1985 to 2018, involving seven radiation workers and 19 members of the public. The accidents caused localized radiation lesions on the hands and fingers.

Dose estimation to eye lens of industrial gamma radiography workers using the Monte Carlo method.

The ICRP Statement on Tissue Reactions (2011), based on epidemiological evidence, recommended a reduction for the eye lens equivalent dose limit from 150 to 20 mSv per year. This paper presents mainly the dose estimations received by industrial gamma radiography workers, during planned or accidental exposure to the eye lens, Hp(10) and effective dose. A Brazilian Visual Monte Carlo Dose Calculation program was used and two relevant scenarios were considered.

Comparison of the effective dose rate to aircrew members using hybrid computational phantoms in standing and sitting postures.

Aircraft crew members are occupationally exposed to considerable levels of cosmic radiation at flight altitudes. Since aircrew (pilots and passengers) are in the sitting posture for most of the time during flight, and up to now there has been no data on the effective dose rate calculated for aircrew dosimetry in flight altitude using a sitting phantom, we therefore calculated the effective dose rate using a phantom in the sitting and standing postures in order to compare the influence of the posture on the radiation protection of aircrew members. We found that although the better description of the posture in which the aircrews are exposed, the results of the effective dose rate calculated with the phantom in the sitting posture were very similar to the results of the phantom in the standing posture.

Organ and effective dose conversion coefficients for a sitting female hybrid computational phantom exposed to monoenergetic protons in idealized irradiation geometries.

The conversion coefficients (CCs) relate protection quantities, mean absorbed dose (DT) and effective dose (E), with physical radiation field quantities, such as fluence (Φ). The calculation of CCs through Monte Carlo simulations is useful for estimating the dose in individuals exposed to radiation. The aim of this work was the calculation of conversion coefficients for absorbed and effective doses per fluence (DT/ Φ and E/Φ) using a sitting and standing female hybrid phantom (UFH/NCI) exposure to monoenergetic protons with energy ranging from 2 MeV to 10 GeV.

Overview of the ICRP/ICRU adult reference computational phantoms and dose conversion coefficients for external idealised exposures.

This paper reviews the ICRP Publications 110 and 116 describing the reference computational phantoms and dose conversion coefficients for external exposures. The International Commission on Radiological Protection (ICRP) in its 2007 Recommendations made several revisions to the methods of calculation of the protection quantities. In order to implement these recommendations, the DOCAL task group of the ICRP developed computational phantoms representing the reference adult male and female and then calculated a set of dose conversion coefficients for various types of idealised external exposures.