Abstract:
In order to analyze the nuclear data uncertainty of
keff for CEFR, the formula of sensitivity to
keff was derived based on the first order perturbation theory, and the multi-group diffusion nodal method was selected to solve the formula. A sensitivity and uncertainty analysis code named SUAPH was developed, based on Neutronics Analysis System for Fast Reactor（NAS）, and verified. Based on the available covariance matrixes, the sensitivity and uncertainty analysis of
keff of the first loading on CEFR was done, and the uncertainty value of calculated
keff due to nuclear data was about 2.02%.
下载:
