Evaluation of Background Radioactivity In Ogbete Coal Mine Dumpsites In Enugu, Nigeria [ READ ]
Nwankpa, Alexander Chinyere
The assessment of naturally occurring radionuclides 238U, 232Th and 40K in Ogbete coal mine dumpsites in Enugu were carried out using gamma-ray spectrometry with high purity germanium detector to determine the natural radionuclide in the dumpsites and to evaluate the hazards these might have on the public. The calculated average activity concentration of 238U, 232Th and 40K in the samples were 18.7 ± 2.9 Bqkg-1, 24.4 ± 2.2 Bqkg-1, and 164.4 ± 17.3 Bqkg-1 respectively. The mean activity concentration of 238U, 232Th and 40K in the present study is much lower than the world-wide average values of 33 Bqkg-1, 45 Bqkg-1 and 420 Bqkg-1 respectively. The present study revealed that the calculated average absorbed dose rate, indoor annual effective dose rate and outdoor annual effective dose were found as 31.2 nGyh-1, 0.15 mSvy-1 and 0.04 mSvy-1 respectively. The mean values of the absorbed dose rate, the indoor and outdoor annual effective dose rates are much lower than the world average recommended safety limits. The International Commission on Radiological Protection (ICRP) has recommended the annual effective dose equivalent limit of 1mSvy-1for the individual members of the public and 20mSvy-1 for the radiation workers. Therefore it can be concluded that the present study area is radiologically safe from radiation hazards and will pose no harmful effects to the environmental and the living population.
Nwankpa, Alexander Chinyere
The assessment of naturally occurring radionuclides 238U, 232Th and 40K in Ogbete coal mine dumpsites in Enugu were carried out using gamma-ray spectrometry with high purity germanium detector to determine the natural radionuclide in the dumpsites and to evaluate the hazards these might have on the public. The calculated average activity concentration of 238U, 232Th and 40K in the samples were 18.7 ± 2.9 Bqkg-1, 24.4 ± 2.2 Bqkg-1, and 164.4 ± 17.3 Bqkg-1 respectively. The mean activity concentration of 238U, 232Th and 40K in the present study is much lower than the world-wide average values of 33 Bqkg-1, 45 Bqkg-1 and 420 Bqkg-1 respectively. The present study revealed that the calculated average absorbed dose rate, indoor annual effective dose rate and outdoor annual effective dose were found as 31.2 nGyh-1, 0.15 mSvy-1 and 0.04 mSvy-1 respectively. The mean values of the absorbed dose rate, the indoor and outdoor annual effective dose rates are much lower than the world average recommended safety limits. The International Commission on Radiological Protection (ICRP) has recommended the annual effective dose equivalent limit of 1mSvy-1for the individual members of the public and 20mSvy-1 for the radiation workers. Therefore it can be concluded that the present study area is radiologically safe from radiation hazards and will pose no harmful effects to the environmental and the living population.
