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 />
means, generally by scientific judgment using all relevant information available. In<br />
the case <strong>of</strong> a measurement <strong>of</strong> activity in the total body or in a biological sample, Type<br />
A uncertainties are generally taken as those that arise only from counting statistics and<br />
can be described by the Poisson distribution, while Type B components <strong>of</strong> uncertainty<br />
are taken as those associated with all other sources <strong>of</strong> uncertainty.<br />
(360) Examples <strong>of</strong> Type B components for in vitro measurements include the<br />
quantification <strong>of</strong> the sample volume or weight; errors in dilution and pipetting;<br />
evaporation <strong>of</strong> solution in storage; stability and activity <strong>of</strong> standards used for<br />
calibration; similarity <strong>of</strong> chemical yield between tracer and radioelement <strong>of</strong> interest;<br />
blank corrections; background radionuclide excretion contributions and fluctuations;<br />
electronic stability; spectroscopy resolution and peak overlap; contamination <strong>of</strong><br />
sample and impurities; source positioning for counting; density and shape variation<br />
from calibration model and assumptions about homogeneity in calibration (Skrable et<br />
al, 1994). These uncertainties apply to the measurement <strong>of</strong> activity in the sample.<br />
With excretion measurements, the activity in the sample is used to provide an<br />
estimate <strong>of</strong> the subject’s average excretion rate over 24 hours for comparison with the<br />
model predictions. If the samples are collected over periods less than 24 hours then<br />
they should be normalised to an equivalent 24 hour value. This introduces additional<br />
sources <strong>of</strong> Type B uncertainty relating to biological (inter-and intra-subject)<br />
variability and sampling procedures, which may well be greater than the uncertainty<br />
in the measured sample activity. Sampling protocols can be designed to minimize the<br />
sampling uncertainty, as shown by Sun et al (1993) for plutonium urinalysis and<br />
Moeller and Sun (2006) for indoor radon exposure.<br />
(361) In vivo measurements can be performed in different geometries (whole body<br />
measurements, and organ or site-specific measurement such as measurement over the<br />
lung, thyroid, skull, or liver, or over a wound. Each type <strong>of</strong> geometry needs<br />
specialized detector systems and calibration methods. The IAEA (1996a) and the<br />
ICRU (2003) have published reviews <strong>of</strong> direct bioassay methods that include<br />
discussions <strong>of</strong> sensitivity and accuracy <strong>of</strong> the measurements.<br />
(362) Examples <strong>of</strong> Type B components for in vivo monitoring include counting<br />
geometry errors; positioning <strong>of</strong> the individual in relation to the detector and<br />
movement <strong>of</strong> the person during counting; chest wall thickness determination;<br />
differences between the phantom and the individual or organ being measured,<br />
including geometric characteristics, density, distribution <strong>of</strong> the radionuclide within the<br />
body and organ and linear attenuation coefficient; interference from radioactive<br />
material deposits in adjacent body regions; spectroscopy resolution and peak overlap;<br />
electronic stability; interference from other radionuclides; variation in background<br />
radiation; activity <strong>of</strong> the standard radionuclide used for calibration; surface external<br />
contamination <strong>of</strong> the person; interference from natural radioactive elements present in<br />
the body; and calibration source uncertainties (IAEA, 1996a; Skrable et al, 1994).<br />
(363) For partial body measurements it is generally difficult to interpret the result in<br />
terms <strong>of</strong> activity in a specific organ because radiation from other regions <strong>of</strong> the body<br />
may be detected. Interpretation <strong>of</strong> such measurements requires assumptions<br />
concerning the biokinetics <strong>of</strong> the radionuclide and any radioactive progeny produced<br />
in vivo. An illustration using 241 Am is given in the IAEA Safety Series Report on<br />
Direct Methods for Measuring <strong>Radionuclides</strong> in the Human Body (IAEA, 1996a). A<br />
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