Abstract
*This paper illustrates an application of a severe accident analysis code, MAAP, to the uncertainty analysis of fission products (FPs) behaviors in case of severe reactor accidents. The MAAP code is a system level computer code capable of performing integral analyses of potential severe accident progressions in nuclear power plants, whose main purpose is to support Level 2 probabilistic safety assessment or severe accident management strategy developments. The code employs lots of user-options for supporting sensitivity and uncertainty analysis. The present application is mainly focused on determining an estimate of the FPs in release and transport processes and relative importance of the dominant contributors to the predicted FPs. Key modeling parameters and phenomenological models employed for the present uncertainty analysis are closely related to FP release correlations, vapor-aerosol equilibrium, vapor-surface equilibrium for a re-vaporization calculation, and aerosol decontamination factors. The Korean standardized nuclear power plant, OPR-1000, has been used as a reference plant for the analysis.
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