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

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EXTERNAL RADIATION SAFETY 575<br />

for a pure high-energy beta emitter, the bremsstrahlung produced in the shield must<br />

be considered in the shielding design.<br />

Neutron shielding is based on slowing down fast neutrons <strong>to</strong> thermal energies<br />

and then absorbing the thermal neutrons. Low-a<strong>to</strong>mic-numbered materials, such<br />

as water, and hydrogenous compounds, such as paraffin, are effective slowing-down<br />

materials. The thermalized neutrons are most readily absorbed by materials that have<br />

a high absorption cross section, such as boron or cadmium. In designing shielding<br />

against neutrons, it must be remembered that absorption of neutrons can lead <strong>to</strong><br />

capture gammas and <strong>to</strong> induced radioactivity and the consequent production of<br />

gamma radiation.<br />

Although radiation protection measures can be designed <strong>to</strong> reduce radiation dose<br />

<strong>to</strong> levels approaching that of the natural background, expenditure of resources <strong>to</strong><br />

do this may be wasteful since the benefits that accrue from such low doses are less<br />

than the benefits that might result from expenditure of these resources in other<br />

avenues. Accordingly, we optimize the degree of radiation protection at the level at<br />

which the benefits are equal <strong>to</strong> the cost of protection.<br />

m Problems<br />

10.1. A Po–Be neutron source emits 107 neutrons/s of average energy 4 MeV. The<br />

source is <strong>to</strong> be s<strong>to</strong>red in a paraffin shield of sufficient thickness <strong>to</strong> reduce the<br />

fast flux at the surface <strong>to</strong> 10 neutrons/cm2 /s. Consider paraffin <strong>to</strong> be essentially<br />

CH2 (for the purpose of this problem) and <strong>to</strong> have a density of 0.89 g/cm3 .<br />

(a) What is the minimum thickness of the paraffin shield?<br />

(b) If the slowing-down length is 6 cm, the thermal diffusion length is 3 cm,<br />

and the diffusion coefficient is 0.381 cm, what will be the thermal-neutron<br />

leakage flux at the surface of the shield?<br />

(c) What is the gamma-ray dose rate, due <strong>to</strong> the hydrogen-capture gammas, at<br />

the surface of the paraffin shield?<br />

10.2. An X-ray therapy machine operates at 250 kVp and 20 mA. At a target <strong>to</strong> skin<br />

distance of 100 cm, the dose rate is 0.2 Gy/min. The workload is 100 Gy/wk. The<br />

X-ray tube is constrained <strong>to</strong> point vertically downward. At a distance of 4 m from<br />

the target is an uncontrolled waiting room. Calculate the thickness of lead <strong>to</strong> be<br />

added <strong>to</strong> the wall if the <strong>to</strong>tal thickness of the wall (which is made of hollow tile<br />

and plaster, density 2.35 g/cm3 ) is 2 in. (5 cm).<br />

10.3. A7.4 × 1013 Bq (2000 Ci) 60Co teletherapy unit is <strong>to</strong> be installed in an existing<br />

concrete room in the basement of a hospital so that the source is 4 m from the<br />

north and west walls—which are 30 in. thick. Beyond the north wall is a fully<br />

occupied controlled room. Beyond the west wall is a public parking lot. The<br />

useful beam is <strong>to</strong> be directed <strong>to</strong>ward the north wall for a maximum of 5 hours<br />

per week during radiation therapy. The beam will be directed at the west wall<br />

1 hour per week. Considering only the radiation from the primary beam, how<br />

much additional shielding, if any, is required for each of the walls?

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