[en] The objectives of this study on the application of statistical techniques to the analysis of reactor safety codes are the identification of the input variables which have a significant influence on the output variables (sensitivity analysis) and the determination of the effect of uncertainty in input values on the output variables. The Latin hypercube sampling (LHS) procedure is presented as an input value selection procedure. The partial rank correlation coefficient (PRCC) coupled with the LHS procedure is presented as a quantitative measure of sensitivity. An examination of the PRCC variability and an analysis of TRAC for a Semiscale test are presented