Propagation of nuclear data uncertainties in fuel cycle calculations using MONTE-CARLO Technique

摘要

The uncertainty propagation in fuel cycle calculations due to Nuclear Data (ND) is a important important issue for : issue for :ud• Present fuel cycles (e.g. high burnup fuel programme)ud• New fuel cycles designs (e.g. fast breeder reactors and ADS)udDifferent error propagation techniques can be used:ud• Sensitivity analysisud• Response Response Surface Method Surface Methodud• Monte Carlo techniqueudThen, p p , , in this paper, it is assessed the imp y pact of ND uncertainties on the decay heat and radiotoxicity in two applications:ud• Fission Pulse Decay ( y Heat calculation (FPDH)ud• Conceptual design of European Facility for Industrial Transmutation (EFIT)