arXiv · 1502.04723
Experimental and Simulation of Gamma Radiation Dose Rate for High Exposure Building Material
Abstract
Natural radioactivity concentrations in high exposure building materials are commonly used in Iran, which is measured a direct exposure by using {\gamma}-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.
Explore related subjects
Keep this discovery
Akbar Abbasi, Mustfa Hassanzadeh. 2014-10-27. Experimental and Simulation of Gamma Radiation Dose Rate for High Exposure Building Material. https://arxiv.org/abs/1502.04723
Cite the original work for its findings. Save a collection to share your selection of sources.