Uncertainties assessment in technological parameters of PWR core

In this paper an uncertainty propagation methodology is applied to PWR nuclear power plant core to assess the impact on technological parameters uncertainties (pellet diameter, pellet density and conductivity, coolant temperature, etc.) into design parameters, like maximum pellet or cladding temperatures, reactivity coefficients, boron concentration or peak factors and to compare it with the impact produced by cross-section uncertainties for a few isotopes like Pu-239, U-235, U-238 or H. This analysis was done by whole core simulations with the SEANAP system, developed at the Politechnical University of Madrid.