Uncertainty analysis of CsI distribution for typical CANDU6 station blackout accident

Abstract

This paper illustrates an application of a severe accident analysis code, ISAAC (Integrated Severe Accident Analysis Code for the CANDU plants), to the uncertainty analysis of fission product behaviors during a severe reactor accident. The ISAAC code is a system-level computer code capable of performing integral analyses of potential severe accident progressions in nuclear power plants, and whose main purpose is to support a level 2 probabilistic safety assessment or severe accident management strategy developments. The code employs lots of user options for supporting sensitivity and uncertainty analyses. The present application is mainly focused on determining an estimate of the fission products in the release and transport processes and the relative importance of the dominant contributors to the predicted fission products. The key modeling parameters and phenomenological models employed for the present uncertainty analysis are closely related to the fission product release correlations, vapor–aerosol equilibrium, vapor–surface equilibrium for a revaporization calculation, and aerosol decontamination factors. A typical CANDU6 type plant, the Wolsong nuclear power plant, was used as a reference plant for the analysis.