Radiation Shielding and Dose

3 Radiation Shielding and Dose 8.3.3.1 Geometric Attenuation of Radiation 

If an accident occurs, people are protected from radiation by materials, distance., nnd limited exposure times. 

The dose from a line of radiation can be easily calculated from the dose from a point source by adding the dose from many 

The attenuation factor for a receptor at the center of a finite plane uniform source of radiation is given by equation 8.3-7, where b is the radius and z is the height of the receptor above the plane. If there is 

This discussion of geometric effects ignored the attenuation of radiation by material through which the radiation must travel to reach the receptor. The number of particles, dN, penetrating material, equals the number of particles incident N times a small penetration distance, dx, divided by the mean free path length x of the type of particle in the type of material (equation 8.3-8). Integrating gives the transmission coefficient for the radiation (equation 8.3-9). 

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