Activity and composition of irradiated materials: assessment of their sensitivity to input parameters

The paper evaluates the influence of the input data uncertainties on the radiation characteristics and composition of spent nuclear fuel (SNF) and radioactive waste (RW). Multivariate calculations were performed in the nuclide kinetics TRACT software and the uncertainty management MOUSE software package. Based on these calculations, the paper evaluates the specific activity and composition of SNF irradiated in a WWER-440 reactor and the specific activity of reactor graphite irradiated in a RBMK-1000 reactor in terms of their sensitivity to the input parameters (initial composition of materials and irradiation history).