Abstract:
Under the same parameters, the Monte Carle codes MCNP5 and EGSnrc were used to calculate the dose field distribution. Measurements of the dose field distributions about the source were performed using LiF thermoluminescent dosimeters(GR-200) in PMMA. Compared with the results of measurements, The MCNP5 and EGSnrc were different in particle transport principle, geometry description and material cross data. The two methods’ results still accorded with the measurements. The EGSnrc performance was better.These two M-C codes were very consistent in calculating dose field distribution of seed source. EGSnrc could got more accurate dose dates.