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

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EXTERNAL RADIATION SAFETY 565<br />

Gamma rays (capture gammas) are almost always produced in the neutron absorption<br />

reactions. The average energy of capture gammas in concrete is 3.6<br />

MeV.<br />

Shielding design of high-energy radiotherapy facilities is based on well-known<br />

principles of bremsstrahlung production, interaction of pho<strong>to</strong>ns with matter, neutron<br />

production, and neutron interactions, including absorption and activation.<br />

However, the application of these principles <strong>to</strong> the design of a particular facility is<br />

a very complex undertaking. Detailed application of these principles may be found<br />

in several applied publications, such as NCRP 144, NCRP 147, and NCRP 151. The<br />

complexity of shielding design for high-energy radiation therapy facilities makes<br />

shielding design an ideal candidate for computerization, and numerous computer<br />

codes may be found in the literature.<br />

Airborne Contaminant Production<br />

Interaction of energy by the atmosphere from environmental radiation fields can<br />

lead <strong>to</strong> radiolytic dissociation of oxygen and nitrogen molecules in the air. The<br />

resulting disrupted molecules can recombine <strong>to</strong> form ozone, nitrogen oxide, and<br />

nitrogen dioxide. Ozone, whose OSHA permissible exposure level (PEL) is 0.1 parts<br />

per million (ppm), and nitrogen dioxide, whose PEL is 5 ppm, are of concern because<br />

of their relatively high <strong>to</strong>xicity. Neutrons can interact with the 40 Ar constituent<br />

in ordinary air <strong>to</strong> produce 110-minute half-lived 41 Ar, and with atmospheric dusts<br />

<strong>to</strong> produce airborne radioactive particles. According <strong>to</strong> NCRP 147, ventilation of a<br />

normal clinical treatment room at a rate of three air changes per hour is sufficient<br />

for health protection.<br />

Beta Shielding<br />

Two fac<strong>to</strong>rs must be considered in designing a shield against high-intensity<br />

radiation—namely, the beta particles and the bremsstrahlung that are generated<br />

due <strong>to</strong> absorption in the source itself and in the shield. Because of these fac<strong>to</strong>rs,<br />

the beta shield consists of a low-a<strong>to</strong>mic-numbered substance (<strong>to</strong> minimize the production<br />

of bremsstrahlung) sufficiently thick <strong>to</strong> s<strong>to</strong>p all the betas, followed by a<br />

high-a<strong>to</strong>mic-numbered material thick enough <strong>to</strong> attenuate the bremsstrahlung intensity<br />

<strong>to</strong> an acceptable level.<br />

TABLE 10-10. Tenth Value Layers (TVLs) of Concrete for Patient-Scattered Radiation at 90 ◦<br />

Scattering Angle<br />

ACCELERATOR VOLTAGE (MV) TVL (cm)<br />

4 17<br />

6 17<br />

10 18<br />

Reproduced with permission of the National Council on Radiation Protection and Measurements from Structural<br />

Shielding Design and Evaluation for Megavoltage X- and Gamma-Ray Radiotherapy Facilities. Bethesda, MD: National<br />

Council on Radiation Protection & Measurement; 2005. NCRP Report 151.

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