Analysis of internal gamma-ray dose to the public from brick as building material in Tamil Nadu, India

Abstract

Abstract Natural radioactivity due to 238U, 232Th and 40K in brick samples from Tamil Nadu was determined using gamma-ray spectrometry. The mean activity concentrations of 238U, 232Th and 40K, 69 ± 6, 62 ± 6 and 462 ± 23 Bq kg−1, are slightly greater than the world recommended limits of 35, 45 and 420 Bq kg−1, respectively, and they are compared with a similar work carried out across the world. The radiological parameters such as radium equivalent activity, Raeq (193 ± 17 Bq kg−1), internal hazard index, Hin (0.71 ± 0.06), and activity utilisation index, AUI (1.43 ± 0.13), was lower, whilst absorbed dose rate, DRin (89 ± 8 nGy h−1), annual effective dose equivalent, AEDEin (0.43 ± 0.04 mSv y−1), and excess lifetime cancer risk, ELCRin (1.52 ± 0.13 mSv y−1), are slightly greater than the world’s recommended limit. Bi-variate statistical analysis was performed to corroborate the relationship between radionuclides and radiological hazards.