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Radiation Protection Dosimetry Advance Access originally published online on August 24, 2005
Radiation Protection Dosimetry 2006 118(1):93-96; doi:10.1093/rpd/nci332
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© The Author 2005. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oxfordjournals.org

Exposure to radiation from the natural radioactivity in Jordanian building materials

J. Al-Jundi*, W. Salah, M. S. Bawa'aneh and F. Afaneh

Department of Physics, The Hashemite University, P. O. Box 150459, Zarqa, Jordan

* Corresponding author: jaj{at}hu.edu.jo

Received January 25, 2005, amended July 4, 2005, accepted July 9, 2005

The natural radioactivity due to the presence of 226Ra, 232Th and 40K in selected building materials used in Jordanian building constructions has been measured using gamma-ray spectrometer with a Hyper Pure germanium detector. The average activity concentrations observed in different building materials ranged from 27.7 ± 7.5 to 70.4 ± 2.8, 5.9 ± 0.67 to 32.9 ± 3.9 and 30.8 ± 0.87 to 58.5 ± 1.5 for 226Ra, 232Th and 40K, respectively. The activity concentrations of 226Ra measured in fine aggregates was found to be among the highest values obtained in this work. The ranges of the calculated Ra-equivalent were found to be lower than those values recommended for construction materials (370 Bq kg–1). The average internal and external hazard indices were found to be <1. The average of the calculated annual gonadal equivalent dose was found to be 198 µSv y–1. Results indicate no significant radiological hazards arise from using such materials in building construction.


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