Shielding design for a research facility in the IEA-R1 reactor

This work presents the final results of a set of simulations run to achieve the most efficient shielding design within initial premise: low cost piecewise materials so to attain to the disposed budget and to allow future improvements in and around the facility. Simulations were performed by DOT 3.5 transport code and ISODOSE code was used convert radiation fluxes into dose. As long as the design was defined, MCNP code was employed to evaluate dose miscount derived by geometric modeling constrains which are inherent to DOT 3.5. (author)