03.06.2013 Views

Occupational Intakes of Radionuclides Part 1 - ICRP

Occupational Intakes of Radionuclides Part 1 - ICRP

Occupational Intakes of Radionuclides Part 1 - ICRP

SHOW MORE
SHOW LESS

You also want an ePaper? Increase the reach of your titles

YUMPU automatically turns print PDFs into web optimized ePapers that Google loves.

4623<br />

4624<br />

4625<br />

4626<br />

4627<br />

4628<br />

4629<br />

4630<br />

4631<br />

4632<br />

4633<br />

4634<br />

4635<br />

4636<br />

4637<br />

4638<br />

4639<br />

4640<br />

4641<br />

4642<br />

4643<br />

4644<br />

4645<br />

4646<br />

4647<br />

4648<br />

4649<br />

4650<br />

4651<br />

4652<br />

4653<br />

4654<br />

4655<br />

4656<br />

4657<br />

4658<br />

4659<br />

4660<br />

4661<br />

4662<br />

4663<br />

4664<br />

4665<br />

4666<br />

4667<br />

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 />

128

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!