One-hundred-fifty-one samples of six types of building materials were collected from different locations of the Tiruvannamalai District, Tamilnadu, and were analyzed using a gamma ray spectroscopy system. From the results, the highest values observed in the specific activities of 226 Ra, 232 Th and 40 K were 116.1 (soil) 106.67 (sand) and 527.533 (tiles) in Bq kg −1 , while the lowest values observed in the specific activities of the same radionuclides were 35.73, 37.75 and 159.83 for cement in Bq kg −1 , respectively. The potential radiological hazards were assessed by calculating the radium equivalent activity (Ra eq), the indoor absorbed gamma dose rate (D R), the annual effective dose rate (H R), the activity utilization index (I), the alpha index (I ␣), the gamma index (I ␥), and the external hazard (H ex) and internal hazard (H in) indices. The estimated mean value of the absorbed dose rate of 148.35 nGy h −1 is slightly higher than the world average value of 84 nGy h −1 , and the annual effective dose in the studied samples is 0.1824 mSv y −1 , which is lower than the recommended limit. Multivariate statistical methods are applied to determine the existing relationship between radionuclides and radiological health hazard parameters and to identify the maximum contribution of radionuclide in radioactivity. The values of the hazard indices were below the recommended levels; therefore, it is concluded that the buildings constructed from such materials are safe for the inhabitants. The findings from this research will be useful to assess the radiation hazards of building materials in humans.
The present study aimed to measure the activity concentration of natural radionuclides in the locally used building materials from Kilpenthaur, Tiruvannmalai Dist, Tamilnadu, India was investigated with an aim of evaluating the radiation hazard arising due to the use of these materials in the construction of dwellings. The concentrations of natural radionuclides Ra, Th and K in four types of building materials have been 226 232 40 measured by gamma spectrometry using NaI (Tl) 3" x 3"detector. The estimated radium equivalent activity (Ra), criteria formula (C), indoor absorbed gamma dose rate (D), annual effective dose rate (H), annual eq R R R gonadal dose equivalent (AGDE), activity utilization index (AUI), representative level index (RLI), excess lifetime cancer risk (ELCR), Internal and Extrnal Radiation hazard indeces (H & H) alphaindex (I) and in ex gammaindex (I) were lower than the recommended safe limit and are comparable with results from similar studies conducted in other countries. Therefore, the use of these building material samples under investigation in the construction of dwellings is considered to be safe for inhabitants.
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