Experimental and Simulation of Gamma Radiation Dose Rate for High Exposure Building Material
arXiv:1502.04723
Abstract
Natural radioactivity concentrations in high exposure building materials are commonly used in Iran, which is measured a direct exposure by using γ-ray spectrometry. The values for 226Ra, 232Th and 40K were in the ranges 3.8 - 94.2, 6.5 - 172.2 and 556.9 - 1539.2 Bqkg-1, respectively. The absorbed dose rates in the standard dwelling room due to 238U, 232Th series and 40K were calculated with MCNPX code. The simulation and experimental results were between 7.95 - 41.74 and 8.36 - 39.99 nGy h-1, respectively. These results were compared with experimental outing and there was overlap closely. The simulation results are able to develop for any kind of dwelling places.
This paper has been withdrawn by the author due to a crucial sign error in equation 1