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 />
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)