Article

Journal of Exposure Science and Environmental Epidemiology (2009) 19, 502–514; doi:10.1038/jes.2008.40; published online 2 July 2008

Radiation dose assessment of exposure to depleted uranium

Wei Bo Lia, Udo C Gerstmanna, Vera Höllriegla, Wilfried Szymczaka, Paul Rotha, Christoph Hoeschena and Uwe Oeha

aInstitute of Radiation Protection, Helmholtz Zentrum München, German Research Center for Environmental Health (GmbH), Neuherberg, Germany

Correspondence: Dr. WB Li, Institute of Radiation Protection, Helmholtz Zentrum München, German Research Center for Environmental Health (GmbH), Neuherberg D-85764, Germany. Tel.: +49 89 3187 3314; Fax: +49 89 3187 2517; E-mail: wli@helmholtz-muenchen.de

Received 17 March 2008; Accepted 24 May 2008; Published online 2 July 2008.

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Abstract

Depleted uranium (DU) is claimed to contribute to human health problems, known as the Gulf War Syndrome and the Balkan Syndrome. Quantitative radiation dose is required to estimate the health risk of DU materials. The influences of the solubility parameters in the human alimentary tract and the respiratory tract systems and the aerosol particles size on the radiation dose of DU materials were evaluated. The dose conversion factor of daily urinary excretion of DU is provided. The retention and excretion of DU in the human body after a contamination at a wound site were predicted. Dose coefficients of DU after ingestion and inhalation were calculated using the solubility parameters of the DU corrosion products in simulated gastric and simulated lung fluid, which were determined in the Helmholtz Zentrum München. 238U is the main radiation dose contributor per 1 Bq of DU materials. The dose coefficients of DU materials were estimated to be 3.5 times 10-8 and 2.1 times 10-6 Sv Bq-1 after ingestion and inhalation for members of the public. The ingestion dose coefficient of DU materials is about 75% of the natural uranium value. The inhalation dose coefficient of DU material is in between those for Type M and Type S according to the category for inhaled materials defined by the International Commission on Radiological Protection. Radiation dose possibly received from DU materials can directly be estimated by using the dose conversion factor provided in this study, if daily urinary excretion of DU is measured.

Keywords:

depleted uranium, biokinetic modeling, internal dose, aerosol, wound model, radiaton exposure

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