Sensitivity and uncertainty studies for the alfred lead cooled fast reactor core

The paper presents sensitivity and uncertainty analysis for the Advanced Lead-cooled Fast Reactor Demonstrator (ALFRED) concept using its publicly available core design parameters. Three important reactivity coefficients (coolant temperature, cladding expansion and fuel temperature) are determined by two different methodologies, the central difference direct perturbation method (with the Serpent Monte Carlo code) and the linear perturbation theory (with both the Serpent code and the SCALE code system), both in infinite assembly lattice and full core models. Comparison of the results is presented and the modeling and methodological differences are discussed. Physical phenomenas behind the reactivity coefficient are analyzed through the observed changes in the spectrum, the homogenized cross section and the energy dependent sensitivity coefficients. Finally, the standard deviation of the effective multiplication factor resulted from the uncertainty of nuclear parameters is quantified.