BIO Web Conf.
Volume 14, 2019The 12th International Conference on the Health Effects of Incorporated Radionuclides (HEIR 2018)
|Number of page(s)||3|
|Section||Biokinetics and Bioaccumulation of Radionuclides: Oral presentations|
|Published online||07 May 2019|
Biokinetic analyses of the latest actinide model for internal dose assessment after an accidental inhalation at a nuclear facility in Oarai, Japan
National Institutes for Quantum and Radiological Science and Technology (QST), National Institute of Radiological Sciences (NIRS), 4-9-1 Anagawa, Inage-ku
* Corresponding author: email@example.com
An accidental inhalation of actinide nuclides, e.g. plutonium and americium, by 5 workers occurred due to an accident at Oarai Research and Development Institute, Japan Atomic Energy Agency in June 2017. Although wearing half-face masks, overalls and gloves, the workers possibly inhaled the radionuclides through tiny gaps between their faces and masks. In vivo counting by using a lung monitor and bioassay measurements for urinal and faecal samples have been performed at the National Institute of Radiological Sciences (NIRS) to assess their intake amounts and internal doses. Decorporation agents, i.e. Ca- and/or Zn-DTPA, were intravenously administered to the all workers for the purpose of enhancing the urinal excretion of actinide nuclides in blood, leading to difficulty in internal dose assessment because the biokinetics may deviate from the general model prediction. The effective dose of the worker who received the highest exposure is currently estimated, still as an initial assessment, to be less than 200 mSv based on previous biokinetic models recommended by International Commission on Radiological Protection (ICRP) [1–3]. The modified biokinetic models for plutonium [4, 5], however, had been proposed to reflect data become newly available since development of the previous models. Recently, ICRP also has published some relevant recommendations describing revised biokinetic models for several elements as the Occupational Intakes of Radionuclides (OIR) series [6-8]. In this study, as part of our effort on improvement of the internal dose assessment for the workers, biokinetic characteristics after inhalation of Pu-239 and Am-241 based on the latest models are compared with those based on the previous models.
Simultaneous differential equations written according to the previous/latest models shown in Table 1 were numerically analysed by using a commercial software, EQUATRAN-G (Omega Simulation, Japan). Absorption type of the respiratory models was selected to be Type M, and particle size in aerosol was selected to be 1, 5, 10, 15 or 20 μm in activity median aerodynamic diameter (AMAD). Relationships between AMAD and activity ratio, [(Excreted activity in faeces collected over first 5 days)/(Residual activity in the lung (the thoracic airways and the thoracic lymph nodes) at third day after intake)], were compared between the previous and latest models.
Previous and latest biokinetic models used for comparison.
Relationships between AMAD and the activity ratio are shown in Figure 1 (a) Pu-239 and (b) Am-241, resulting in large differences between the previous and latest models. This activity ratio is one of important facts, obtained from results of in vivo counting and bioassay measurements, to estimate AMAD, especially as in this case that information on particle size in aerosol is unavailable. The actual activity ratio of Am-241 measured after the accident was about 34, corresponding to more than 17 μm and 12 μm based on the previous and latest models. The results of this study demonstrate that AMAD is overestimated based on the previous models, leading to underestimation of actinide amount absorbed from respiratory tracts into blood because smaller particle in aerosol is likely to be inhaled deeply into the lungs. Therefore, it is clearly worth considering to apply the latest models in future studies for improvement of the internal dose assessment for the workers.
Relationships between AMAD and activity ratio: [(Faecal activity for 5 days)/(Lung activity at third day)].
- ICRP Publication 30 (Part 1), Ann. ICRP 2 , 3-4 (1979) ; [Google Scholar]
- ICRP Publication 66, Ann. ICRP 24 , 1-3 (1994) ; [Google Scholar]
- ICRP Publication 67, Ann. ICRP 23 , 3-4 (1993) ; [Google Scholar]
- Leggett, R.W., Radiat. Prot. Dosim. 106 , 103-120 (2003) ; [CrossRef] [Google Scholar]
- Leggett, R.W. et al, Radiat. Res. 164 , 111-122 (2005) ; [CrossRef] [PubMed] [Google Scholar]
- ICRP Publication 130, Ann. ICRP 44 , 2 (2015) ; [Google Scholar]
- ICRP Publication 134, Ann. ICRP 45 , 3-4 (2016) ; [Google Scholar]
- ICRP Publication 137, Ann. ICRP 46 , 3-4 (2017) ; [Google Scholar]
- ICRP Publication 100, Ann. ICRP 36 , 1-2 (2006) [PubMed] [Google Scholar]
© The Authors, published by EDP Sciences, 2019
This is an open access article distributed under the terms of the Creative Commons Attribution License 4.0 (http://creativecommons.org/licenses/by/4.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.
Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.
Initial download of the metrics may take a while.