Severe Accident Analysis of High Pressure Sequences for APR1400 using CINEMA Computer Code

Abstract

As an integrated computer code development in Korea, CINEMA (Code for INtegrated severe accidEnt Management Analysis) has been developed for a severe accident analysis from an initiation event to a containment failure. The basic goal of this code development is to design a severe accident analysis code package by exploiting the existing domestic DBA (Design Basis Analysis) code system for the severe accident analysis. The CINEMA computer code is composed of CSPACE (Compass, Safety and Performance Analysis CodE for nuclear power plants), SACAP (Severe Accident Containment Analysis Package), and SIRIUS (SImulation of Radioactive nuclide Interaction Under Severe accident), which are capable of core melt progression with thermal hydraulic analysis of the RCS (Reactor Coolant System), severe accident analysis of the containment, and fission product behavior analysis, respectively. For the purpose of CINEMA verification for a real Korean power plant application, severe accident of high-pressure sequences of TLOFW (Total Loss of Feed Water) and SBO (Station Blackout) has been analyzed in this study. This best estimate analysis has been performed to estimate the efficiency of the CINEMA computer code and the predictive qualities of its models from an initiating event to a reactor vessel failure during severe accidents.