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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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