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A respiratory model for uranium aluminide based on occupational data.

R W Leggett1, K F Eckerman, J D Boice

  • 1Oak Ridge National Laboratory, 1060 Commerce Park Oak Ridge, TN, USA. rwl@ornl.gov

Journal of Radiological Protection : Official Journal of the Society for Radiological Protection
|December 13, 2005
PubMed
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Workers exposed to uranium aluminide (UAl(x)) showed delayed dissolution, leading to underestimated intakes. This study provides material-specific parameters for the Human Respiratory Tract Model (HRTM) to improve dose estimations.

Area of Science:

  • Occupational health
  • Radiological protection
  • Nuclear engineering

Background:

  • Epidemiological study of workers at Rocketdyne/Atomics International facility (52-year period).
  • Facility involved in nuclear fuel fabrication, decladding, reactor operations, and disassembly.
  • Documented intakes primarily involved inhalation of enriched uranium (U), fission products, and plutonium (Pu).

Purpose of the Study:

  • Estimate radionuclide intake doses for exposed workers.
  • Investigate the behavior of uranium aluminide (UAl(x)) in workers.
  • Develop material-specific parameter values for the International Commission on Radiological Protection's Human Respiratory Tract Model (ICRP HRTM).

Main Methods:

  • Epidemiological dose estimation for workers.

Related Experiment Videos

  • Analysis of uranium excretion patterns in exposed individuals.
  • Comparison of observed excretion data with ICRP HRTM default absorption types.

    • Main Results:

    • Highest doses estimated for workers exposed to airborne uranium aluminide (UAl(x)) during reactor fuel plate fabrication.
    • Underestimation of intake and lung retention due to delayed dissolution of UAl(x) was identified.
    • Observed urinary excretion of U in removed workers increased, peaked, then declined, consistent with moderately soluble material.

    Conclusions:

    • The dissolution behavior of UAl(x) in the human respiratory tract differs from ICRP HRTM default assumptions.
    • Material-specific parameters are needed for accurate dose assessment of UAl(x) exposure.
    • Findings will improve the accuracy of radiological dose estimations for workers exposed to uranium compounds.