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Scope

1.1 This practice presents a technique for calculating the absorbed dose in a material from knowledge of the radiation field, the composition of the material, (1) and a related measurement. The procedure is applicable for X and gamma radiation provided the energy of the photons fall within the range from 0.01 to 20 MeV.

1.2 A method is given for calculating the absorbed dose in a material from the knowledge of the absorbed dose in another material exposed to the same radiation field. The procedure is restricted to homogeneous materials composed of the elements for which absorption coefficients have been tabulated (2). It also requires some knowledge of the energy spectrum of the radiation field produced by the source under consideration. Generally, the accuracy of this method is limited by the accuracy to which the energy spectrum of the radiation field is known.

1.3 The results of this practice are only valid if charged particle equilibrium exists in the material and at the depth of interest. Thus, this practice is not applicable for determining absorbed dose in the immediate vicinity of boundaries between materials of widely differing atomic numbers. For more information on this topic, see Practice E1249.

1.4 This practice does not consider dose "buildup" due to broad-beam geometry. Such "buildup" depends on the energy spectrum of the radiation field and the effective atomic number of the material. Correction can be made if buildup factors are included in the attenuation calculation. These factors have not been tabulated for a wide range of energies, geometries, and materials (3,4,5). However, this method has utility in providing a quick and relatively simple way of achieving useful approximate results.

1.5 Energy transport computer codes exist that are formulated to calculate absorbed dose in materials more precisely than this method. To use these codes, more effort, time, and expense are required. If the situation warrants, such calculations should be used rather than the method described here.

1.6 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Keywords

Absorbed radiation dose; Dosimetry; Energy deposition-ionizing radiation; Gamma radiation; Threshold detectors-.01 MeV to 20 MeV; X-irradiation; calculating absorbed dose in a material from knowledge of radiation; field/material composition/related measurement, practice; ICS Number Code 17.240 (Radiation measurements)

To find similar documents by ASTM Volume:

12.02 (Nuclear (II), Solar, and Geothermal Energy)

To find similar documents by classification:

17.240 (Radiation measurements Including dosimetry Radiation protection, see 13.280)

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