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

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RADIATION DOSIMETRY 271<br />

6.2. An air ionization chamber whose volume is1Lisused as an environmental moni<strong>to</strong>r<br />

at a temperature of 27◦C and a pressure of 700 <strong>to</strong>rr. What is the exposure rate, in<br />

μC/kg/h and in mR/h, if the saturation current is 10−13 A?<br />

6.3. A beam of 1-MeV gamma rays and another of 0.1-MeV gamma rays each produce<br />

the same ionization density in air. What is the ratio of 1:0.1 MeV pho<strong>to</strong>n<br />

flux?<br />

6.4. Assuming that the specific heat of the body is 1 cal/g/ ◦C, calculate the temperature<br />

rise due <strong>to</strong> a <strong>to</strong>tal body dose of 5 Gy.<br />

6.5. Compute the exposure rate, in mGy/h, at a distance of 50 cm from a small vial<br />

containing 10 mL of an aqueous solution of<br />

(a) 2-GBq (54.1-mCi) 51Cr (b) 2-GBq (54.1-mCi) 24Na, based on the transformation schemes shown below:<br />

6.6. What is the soft tissue dose rate during exposure <strong>to</strong> 25.4 μC/kg/h (100 mR/h) of<br />

0.5-MeV gamma radiation?<br />

6.7. A collimated beam of 0.3-MeV gamma radiation whose energy flux is 5 J/m2 /s is<br />

shielded by 2-cm Pb.<br />

(a) What is the pho<strong>to</strong>n flux incident on the shield, in pho<strong>to</strong>ns cm −2 s −1 ?<br />

(b) What is the exposure rate, mR/h and C/kg/h, in the incident and emergent<br />

beams?<br />

(c) What is the tissue dose rate, mGy/h, in the incident and emergent beams?<br />

6.8. The exposure rate in a beam of 100-keV gamma rays is 25.8 μC/kg (100 mR) per<br />

hour. What is the<br />

(a) pho<strong>to</strong>n flux, in pho<strong>to</strong>ns/cm2 /s?<br />

(b) power density, in W/m2 and mW/cm2 ?<br />

6.9. In an experiment, a 250-g rat is injected with 10-μCi 203 Hg in the form of<br />

Hg(NO3)2. The rat was counted daily in a <strong>to</strong>tal-body counter and the following<br />

equation was fitted <strong>to</strong> the whole-body-counting data<br />

Y = 0.55e −0.346t + 0.45e −0.0346t<br />

where Y is the fraction of the injected dose retained t days after injection. If the<br />

long-lived component of the curve represents clearance from the kidneys while the<br />

short-lived component represents clearance from the rest of the body, calculate<br />

the radiation absorbed dose <strong>to</strong> the whole body and the kidneys if each kidney<br />

weighs 0.7 g. Assume the mercury <strong>to</strong> be uniformly distributed in the whole body

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