Estimating the effective dose from exposures in industrial radiography accidents

Document Type : Original Article

Authors

1 Physics Department, Faculty of Science, University of Birjand, Birjand, Iran

2 Science and Technology Center, Badakhshan, Afghanistan

Abstract

Fast estimation of dose distribution in victims of industrial radiography accidents is important. Thus having a data library from effective dose and absorbed dose data for use in crucial situations can be effective. In this study, the whole body effective dose for two commonly used industrial radiography sources, 192Ir and 60Co, was evaluated using the MCNPX2.6 Monte Carlo code and the adult male voxel phantom ICRP. Simulations were performed in 4 radiation geometries (AP, PA, RLAT, LLAT) and 5 different source heights including ground, middle thigh, lower torso, middle torso, and upper torso. The results of this study show that the effective dose at all heights at distance greater than 100 cm, except for ground level, is independent of source height and relatively consistent. The highest and lowest values of effective dose are associated with the AP and RLAT radiation geometries, respectively. The effective dose at the middle torso in the AP geometry and at a distance of 0.5 cm is 5 and 200 times higher compared to the middle thigh and ground heights, respectively, for both 192Ir and 60Co sources. Using the data obtained in this study, the effective dose for a victim of a 1996 accident in Gilan was estimated to be 200 mSv. The results of this study were compared with the data reported in ICRP145, and the reasons for the differences were investigated.

Keywords

References

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