Experimental and Simulated Effective Dose for Some Building Materials in France

Samir Dziri, Abdellatif Nachab, Abdelmjid Nourreddine, Addil Sellam, Dominique Gelus

Groupe RaMsEs, Institut Pluridisciplinaire Hubert Curien (IPHC), Université de Strasbourg, Strasbourg, France.

DOI: 10.4236/wjnst.2013.32007                

Abstract

The specific radioactivity of several building materials used in France, which is considered a direct exposure to radiation, has been assessed by γ-ray spectrometry. Corrected for coincidence summing and self-absorption effects, the values for ²²⁶Ra, ²³²Th and ⁴⁰K 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.

Keywords

Building Materials; Hazard Indexes; Radium-Equivalent; Absorbed Dose; Annual Effective Dose; MCNPX

Conflicts of Interest

The authors declare no conflicts of interest.

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