Transactions of the Korean Nuclear Society Spring Meeting Taebaek, Korea, May 26-27, 2011
The keff or power distribution estimated by Monte Carlo (MC) method is unavoidably associated with the uncertainties because of the uncertainties of the nuclear cross section data and the its stochastic nature. The statistical uncertainties could be easily controlled by the total number of neutron histories employed in MC runs. On the other hand, there have been various studies to examine quantitatively the effect of the uncertainties of nuclear cross sections. Recently, we presented a new MC formulation for analyzing the uncertainty propagation in MC depletion calculations and the effect of cross section uncertainties on analysis of criticality benchmark problems. In this paper, the MC uncertainty analysis for VENUS-1 experiments is performed to quantifying the effect of nuclear design parameters such as an effective multiplication factor and reaction rates using the sensitivity and uncertainty(S/U) analysis module of McCARD and the available covariance data
