Speaker
Description
The nuclear data are the basic data for reactor burnup calculation. It is significant to study the contribution of their uncertainty to the uncertainty of reactor burnup calculation for improving the safety and economy of reactor. we propagated the uncertainties coming from the nuclear data to the isotopic inventory of sample SF95-4. A Monte Carlo sampling code was developed and used to propagate the decay constant uncertainties, cross-section covariance information and uncertainties of the fission yields. The results showed that the impact of decay constant uncertainties was inappreciable and the contribution of cross-section covariance mostly affected the uncertainties of the actinides. Fission yields appeared to have the largest impact on the uncertainties of the fission products.