Abstract
A new Monte Carlo (MC) formulation aimed at quantifying eects of both statistical and nuclear cross section uncertainties on neutronics design parameters on nuclear systems is presented. The eectiveness of the formulation is examined through computing the contribution of the cross section uncertainties to the variance of the MC estimate on ke of two fast spectrum criticality benchmark problems; GODIVA and JEZEBEL using McCARD as a MC neutronics code and JENDL 3.3 for needed cross section and covariance data. It is shown that the MC formulation is capable of identifying the nuclide and the type of the cross sections that contribute signicantly to, and to elicit the necessary improvement in the existing covariance data to reduce, the uncertainties of the criticality calculations.
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