Experimental and Simulated Effective Dose for Some Building Materials in France

Abstract

The specific radioactivity of several building materials used in France, which is considered a direct exposure to radia tion, has been assessed by γ -ray spectrometry. Corrected for coincidence summing and self-absorption effects, the val ues for 226 Ra, 232 Th and 40 K were in the ranges 4 - 56, 3 - 72 and 9 - 1136 Bq·kg -1 , respectively. The samples were found to have radium-equivalent activities between 5 and 245 Bq·kg -1 . Values of 0.02 - 0.67 for the external and 0.03 - 0.82 for the internal hazard indexes were estimated. The calculated absorbed dose in air agrees closely with MCNPX simulations. The conversion of absorbed dose to annual effective dose gave values between 0.03 - 1.09 mSv·y -1 . All these values are below action limits recommended by the International Commission on Radiological Protection. The materials examined would not contribute a significant radiation exposure for an occupant and thus are acceptable for construction.