Occupational Intakes of Radionuclides Part 1 - ICRP
Occupational Intakes of Radionuclides Part 1 - ICRP
Occupational Intakes of Radionuclides Part 1 - ICRP
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DRAFT REPORT FOR CONSULTATION<br />
the absence <strong>of</strong> specific information, it would be appropriate to assume that intake was<br />
by inhalation for an occupational exposure. The effect <strong>of</strong> assumed route <strong>of</strong> intake on<br />
assessed doses can be large and should be investigated when assessed doses are<br />
significant.<br />
Source term<br />
(368) Assumptions regarding the source term (i.e. the identity <strong>of</strong> the radionuclides<br />
and their relative abundances) may represent major sources <strong>of</strong> uncertainty when<br />
monitoring does not include the measurement <strong>of</strong> all the radioisotopes present in the<br />
working environment. In many situations a worker is exposed to several isotopes <strong>of</strong><br />
the same radionuclide, but monitoring is accomplished through the measurement <strong>of</strong><br />
one <strong>of</strong> the isotopes. For example, lung monitoring <strong>of</strong> uranium through the<br />
measurement <strong>of</strong> 235 U relies on assumptions on the level <strong>of</strong> enrichment. In other<br />
circumstances, assessments <strong>of</strong> exposure to certain radionuclides are based on the<br />
monitoring results <strong>of</strong> a progeny radionuclide in the lungs. For example, monitoring <strong>of</strong><br />
232<br />
Th by measurement <strong>of</strong> a progeny radionuclide relies on assumptions about the<br />
equilibrium <strong>of</strong> radionuclides in the 232 Th decay chain in the material to which the<br />
worker is exposed. Also, exposure to some radionuclides may be based on<br />
measurement <strong>of</strong> a surrogate radionuclide known to be present in the working<br />
environment. For example, lung monitoring <strong>of</strong> 239 Pu may be based on the<br />
measurement <strong>of</strong> 241 Am, using assumptions about the fraction <strong>of</strong> 241 Am, which grows<br />
from 241 Pu.<br />
(369) Information on the chemical form, or mixture <strong>of</strong> forms, <strong>of</strong> an inhaled<br />
radionuclide is needed to help determine an appropriate dissolution model for activity<br />
deposited in the lungs. The dissolution rate in the lungs can represent a major source<br />
<strong>of</strong> uncertainty in a dose assessment, particularly when dose estimates are based on<br />
excretion data alone. For example, if dose estimates are based on urinary excretion<br />
data, then the dose to lungs can sometimes be underestimated by several orders <strong>of</strong><br />
magnitude if the material is incorrectly assumed to be highly soluble or overestimated<br />
by several orders <strong>of</strong> magnitude if the material is incorrectly assumed to have low<br />
solubility. When no direct information is available on the inhaled form <strong>of</strong> a<br />
radionuclide, a combination <strong>of</strong> urinary and faecal data and, where feasible, in vivo<br />
lung measurements may greatly reduce the uncertainty in dose estimates associated<br />
with the chemical form <strong>of</strong> the radionuclide.<br />
<strong>Part</strong>icle size<br />
(370) The particle size can be an important source <strong>of</strong> uncertainty because it<br />
influences the assumed deposition in the respiratory tract. The urinary and faecal<br />
excretion rates depend <strong>of</strong> the particle size because the size influences the transfer <strong>of</strong><br />
unabsorbed particles to the alimentary tract. In some working environments<br />
multimodal aerosols exist within the respirable size range.<br />
6.5.3 Uncertainties in Biokinetic Models<br />
(371) Biokinetic models are used in radiation protection to predict the transfer and<br />
bioaccumulation <strong>of</strong> a radionuclide in various organs and the rate <strong>of</strong> excretion <strong>of</strong> the<br />
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