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 />
measurements. The in vivo detection capability and minimum detection levels <strong>of</strong> in<br />
vivo counting are strongly influenced by the presence <strong>of</strong> 40 K in the body.<br />
(329) Excretion data from uranium and thorium series radionuclides may need<br />
correction for dietary intakes. A ‘blank’ bioassay sample should be obtained from the<br />
workers, prior to the commencement <strong>of</strong> work. When not possible, bioassay samples<br />
from family members or from the population living in the same area should be taken<br />
and analyzed, to allow natural or non-occupational intakes and occupational intakes to<br />
be distinguished (Lipsztein et al, 2003; Lipsztein et al, 2001; Eckerman and Kerr,<br />
1999). In cases <strong>of</strong> positive excreta results resulting from occupational exposures, the<br />
background values should be subtracted from the monitoring results, before dose<br />
calculations. This might not be simple, especially when dealing with faeces<br />
monitoring results. Little et al (2007) describe a Bayesian method to identify a typical<br />
excretion rate <strong>of</strong> uranium for each individual in the absence <strong>of</strong> occupational intakes.<br />
(330) In addition it is important to evaluate the influence <strong>of</strong> radiopharmaceuticals<br />
that may have been administered for diagnostic or therapeutic purposes.<br />
(331) For long lived radionuclides, bioassay monitoring results might carry the<br />
influence <strong>of</strong> intakes identified in preceding monitoring intervals. The retained activity<br />
in the body from previous intakes should be taken into account.<br />
6.3.6 Special monitoring situations<br />
(332) In many situations exposure will be to a single radionuclide or a limited<br />
number <strong>of</strong> radionuclides. For some elements, however, exposures may involve a<br />
number <strong>of</strong> isotopes with different decay properties. Uranium and plutonium illustrate<br />
the potential for exposure to complex mixtures. Various plutonium isotopes are<br />
present in the nuclear industry. Studies have shown a significant difference in isotopic<br />
behaviour <strong>of</strong> plutonium, due to differences in specific activity (Guilmette et al, 1992).<br />
Workers exposed to uranium are always exposed to a mix <strong>of</strong> isotopes, in different<br />
proportions depending on the enrichment level. Knowledge <strong>of</strong> the enrichment is<br />
essential for the correct interpretation <strong>of</strong> bioassay monitoring results.<br />
(333) Special considerations apply when direct bioassay measurements <strong>of</strong><br />
radioactive progeny are used to determine the body content <strong>of</strong> the parent radionuclide<br />
(Section 3.2.3). Significant errors can arise if it is assumed that the progeny are<br />
always in secular equilibrium. For example, the activity <strong>of</strong> 232 Th in the lungs can be<br />
underestimated when determined from direct measurements <strong>of</strong> its 228 Ac, 212 Pb, 212 Bi<br />
and 208 Tl progeny. Differences in lung retention among the measured element and the<br />
radionuclide <strong>of</strong> concern contribute to the uncertainty <strong>of</strong> results. For the same reasons,<br />
activity <strong>of</strong> 232 Th in the lungs can be underestimated when determined from<br />
measurements <strong>of</strong> 220 Rn in breath.<br />
(334) There are also situations when one radionuclide is used as a surrogate for<br />
another, for example for in vivo bioassay monitoring. One example is the<br />
determination <strong>of</strong> the level <strong>of</strong> internally deposited Pu in the lung which is <strong>of</strong>ten<br />
estimated on the basis <strong>of</strong> 241 Am external monitoring <strong>of</strong> the chest. 241 Am generally<br />
accompanies Pu in the work place or is produced in the body by decay <strong>of</strong> 241 Pu. This<br />
procedure is <strong>of</strong>ten appropriate but depending on the solubility characteristics and<br />
isotopic composition <strong>of</strong> the aerosols, the relative clearance rates from the lung might<br />
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