Calculation of absorbed dose and investigation of safety for peoples in neutron laboratory in Amir Kabir University with MCNP code

Authors

10.22052/2.1.7

Abstract

Nuclear radiation protection and safety is one of the most important principles needed to consider in nuclear labs. At this article, Dr. Shahriari Nuclear Laboratory, was selected as a case study for investigation of total absorbed dose at the different points of the lab to determine the safe or hazardous points in it, according to nuclear radiations safety rules. Therefore, the environment of the laboratory was simulated at three levels by MCNP code. At the first level we studied the influence of both gamma and neutron absorbed dose. At levels two and three, effect of all radiations were investigated and calculated. At the end according to the results abstained from three simulation levels, the safe and hazardous points of the laboratory were determined. Finally, based on the method used in this study to determine the safety of the laboratory, recommendations are presented to protect the personnel of similar laboratories.

Keywords


[1] G.Hine, G.Brounell, \"Radiation dosimetry\", New York, Academic press, U.S.A (1961).