Analysis of internal gamma-ray dose to the public from brick as building material in Tamil Nadu, India
Seenuvasan Karthikayini, Ananthanarayanan Chandrasekaran- Public Health, Environmental and Occupational Health
- Radiology, Nuclear Medicine and imaging
- General Medicine
- Radiation
- Radiological and Ultrasound Technology
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.