SUMMARY

The ability to estimate and reconstruct internalized doses remains a challenge due to inability to directly measure radionuclide body burden from internal uptakes. Biokinetic models are therefore required for internal dosimetry calculations, which involve mathematical modeling of the retention and excretion of radionuclides from the body. Historically, the mathematical parameters governing the transfer of radionuclides between organ/tissue compartments of the body constituting biokinetic models have been treated as deterministic. Therefore, to quantify the uncertainty and its impact on computing derived response levels for hazard mapping in consequence management of nuclear and radiological exposure events, this study aims to conduct an expanded statistical treatment of input parameters for inhalation dose coefficients. The REDCAL code was designed to propagate uncertainties through the International Commission on Radiological Protection Publication 66 Human Respiratory Tract Model (HRTM) for inhaled radioactive materials of concern originating from nuclear power plants, radiological dispersal devices, nuclear fallout, and thermoelectric generator exposure events. These scenarios cover a multitude of different chemical forms and particle size ranges for the radionuclides of interest. The data set generated from REDCAL will be used to construct a radionuclide-specific uncertainty profile for use in the Turbo-FRMAC consequence management tool for mapping the hazard levels.