Uncertainty Quantification and Sensitivity Analysis for Coupled VERA-CS and FRAPCON

摘要

LOTUS framework and capabilities are outlined. Brief descriptions of uncertainty quantification and global sensitivity analysis methods Spearman, Pearson, and partial correlation coefficients are presented. The inconsistencies in the models are documented and either justified or given a proposed plan for future investigation. Trial demonstrations of uncertainty quantification and sensitivity analysis are performed on a coupled reactor simulator VERA-CS (1,200 cases) and the fuel performance code FRAPCON (316,800 cases). Results demonstrate ability of LOTUS to calculate 95/95 confidence intervals and correlations coefficients for each individual fuel rod in a depletion case.