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Occupational Intakes of Radionuclides Part 1 - ICRP

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DRAFT REPORT FOR CONSULTATION<br />

suppose the liver is depicted in the parent’s model as two compartments and also in<br />

the progeny radionuclide’s model as two compartments. If the compartments<br />

represent the same physically identifiable portions <strong>of</strong> the liver in both models, e.g.,<br />

hepatocytes and Kuppfer cells, then decays <strong>of</strong> the parent in the two liver<br />

compartments in the parent’s model would be assigned to the corresponding liver<br />

compartments in the progeny radionuclide’s model. However, if the compartments are<br />

defined on a kinetic basis in both models and have no obvious physical interpretation,<br />

it will generally not be evident how the progeny atoms produced in the parent’s liver<br />

compartments should be divided between the progeny’s liver compartments. In such<br />

cases the convention used here is to assign all <strong>of</strong> the progeny atoms to the<br />

compartment with the highest turnover rate, and assume that the progeny radionuclide<br />

is removed from that compartment to the central blood compartment at that rate.<br />

3.6 Medical Intervention<br />

(229) If medical treatment to prevent uptake or enhance excretion is administered,<br />

then the data provided in the models summarised above cannot be used directly to<br />

assess committed effective doses from monitoring information (NCRP, 1980; Gerber<br />

and Thomas 1992; IAEA 1996). In such circumstances a programme <strong>of</strong> special<br />

monitoring (Section 5.5) should be undertaken to follow the retention <strong>of</strong> the particular<br />

contaminant in the person, and these data should be used to make a specific<br />

assessment <strong>of</strong> committed dose.<br />

3.7 Methodology for dose calculations<br />

(230) The general method <strong>of</strong> dose calculation described here is similar as in earlier<br />

<strong>ICRP</strong> Publications (<strong>ICRP</strong>, 1979, 1994b), but some changes were introduced to accord<br />

with <strong>ICRP</strong> Publications (<strong>ICRP</strong>, , 2008) which used MIRD terminology for<br />

radiopharmaceutical dosimetry. In order to provide a consistent internal dosimetry<br />

framework for both radiation protection and nuclear medicine, the standardised<br />

nomenclature and symbols <strong>of</strong> MIRD Pamphlet No. 21 (Bolch et al 2009) used for<br />

protection quantities, and their conventions are followed in this section.<br />

(231) The Commission defines effective dose, E, for adults as:<br />

E<br />

Male<br />

Female<br />

H(<br />

r <br />

<br />

T , 50)<br />

H(<br />

rT<br />

, 50)<br />

wT <br />

<br />

<br />

2<br />

<br />

T<br />

where wT is the tissue weighting factor (Table 2) for the target tissue rT and<br />

H(rT,50) Male and H(rT,50) Female are the committed equivalent doses for the target tissue<br />

rT for the reference male and female, respectively, integrated over 50 years. The<br />

committed equivalent dose in the target tissue for the reference male or female is:<br />

50<br />

( r , 50)<br />

H<br />

( r , t)<br />

dt (2)<br />

<br />

H T<br />

T<br />

0<br />

97<br />

(1)

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