Monte Carlo modelling of radiation transport with PELSHIE Shielding code

In order to perform the final processing of radioactive waste, some estimation related to the contamination degree and/or the radiation dose level, both at the container surface and in the operator lodge, are needed. At INR / Nuclear Fuel Plant Pitesti site these estimations are performed with PELSHIE Shielding code. Starting from the modeling of the source and of the protection shields, the integral radiation dose is obtained; to evaluate these integrals, Monte Carlo methods are used. The paper presents the dose rates obtained by PELSHIE Shielding code calculations for 50 radioactive waste containers processed on the INR / Nuclear Fuel Plant at Pitesti site, as well as the comparison between the calculated dose rates and the experimentally measured ones. (authors)