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Introduction to Health Physics: Fourth Edition - Ruang Baca FMIPA UB

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Evaluation of Radiation Safety Measures 677<br />

Figure 13-3. Whole-body scan, with a<br />

crystal gamma-ray detec<strong>to</strong>r, 2 hours after<br />

ingestion of Tc. (Reproduced with<br />

permission from Beasley TM, Palmer HE,<br />

Nelp WB. Distribution and excretion of<br />

technetium in humans. <strong>Health</strong> Phys.<br />

1966; 12(10): 1425–1435.)<br />

Using the principles described above, <strong>to</strong>gether with data from physiologically<br />

based biokinetic models applied <strong>to</strong> the reference man, tables of IRFs and urinary and<br />

fecal elimination fractions for most radionuclides that were ingested or inhaled were<br />

calculated and <strong>to</strong>gether with the calculational methodology for their application, are<br />

published in Lessard (1987) 1 and in ICRP 78.<br />

In Vivo Bioassay<br />

In vivo bioassay may range from simply measuring the radiation from the thyroid<br />

gland under standardized conditions with a simple detec<strong>to</strong>r such as the Geiger<br />

counter probe, with a scintillation detec<strong>to</strong>r from a health physics surveying instrument,<br />

or with a highly sophisticated, heavily shielded, low-background whole-body<br />

counter. The simple determination may be used in routine “go–no go” moni<strong>to</strong>ring<br />

<strong>to</strong> determine whether a previously established reference level has been reached,<br />

while measurements with the sophisticated system are useful <strong>to</strong> learn how much<br />

and what kind of activity is in the body. A whole-body count directly measures the<br />

radiation emitted from the internally deposited radionuclides. This information is<br />

used <strong>to</strong> determine the nature and location of the radionuclide and <strong>to</strong> quantitatively<br />

estimate the amount in the body, as shown in Figure 13-3. Generally, gamma emitters<br />

whose quantum energy exceeds about 30–50 keV can be determined using in vivo<br />

techniques. When in vivo methods are used <strong>to</strong> determine internal emitters, the in<br />

vivo data are cus<strong>to</strong>marily used as the data of record for demonstrating compliance<br />

with radiation safety regulations.<br />

1 Lessard, E. T. et al. Interpretation of Bioassay Measurements. NUREG/CR-4884, BNL-NUREG-<br />

52063, U.S. Nuclear Regula<strong>to</strong>ry Commission, Washing<strong>to</strong>n, DC, 1987.

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