Experimental and Simulation of Gamma Radiation Dose Rate for High Exposure Building Material
Abbasi, Akbar · Hassanzadeh, Mustfa
Original · EN
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.
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