• burnup
• incertezza
• metodi deterministici
• monte carlo
• neutronica

This work is focused on neutronic investigations of VVER reactors, especially on MOX and LEU assemblies.
Two phases can be identified: the first is a depletion study and the second is an uncertainty and sensitivity analysis.
The purpose of the first part of this thesis was to provide two new solutions to the OECD VVER-1000 burn-up computational benchmark with SERPENT and SCALE (TRITON), which are, respectively, a Monte Carlo and a deterministic code.
The impact on the solutions of the use of modern nuclear data libraries and different depletion Monte-Carlo algorithms was an additional purpose.
The uncertainty and sensitivity analysis was an application of perturbation and statistical methodologies for evaluating the uncertainties associated to the computation of integral reactor parameters typical of VVER (and generally LWRs) reactors using the test cases of the OECD VVER-1000 burn-up computational and UAM benchmarks.