Probabilistic analysis of codes and calculational results in nuclear reactor safety

The input quantities of computer programs within the area of nuclear safety must often be considered as random quantities. From the knowledge of the input performance it is desired to draw conclusions about output performance (e.g.: distributions, confidence bounds, correlations). The application of Monte Carlo methods is introduced and the automatization of probabilistic analysis in program systems is described, based on the experiences in the frame of the modular systems RSYST and SSYST. Furthermore results for various types of nuclear reactor safety calculations are shown