CODE DEVELOPMENT OF SEVERE ACCIDENT SEQUENCE ANALYSIS FOR KOREAN SMALL INTEGRAL REACTOR AND ITS APPLICATION

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Rae-Joon Park
Dong Gun Son
Sang Ho Kim
Hyung Tae Kim
ChangHwan Park

Abstract

The Korean small integral reactor of SMART (System-integrated Modular Advanced ReacTor) has been developed, which contains core, reactor coolant pumps, steam generators and pressurizer within a single reactor pressure vessel. In the code development of severe accident sequence analysis for the SMART, a CINEMA (Code for INtegrated severe accidEnt ManagementAnalysis)-SMARTcomputer code has been developing from an initiation event to a containment failure including fission product behavior in the vessel and the containment. The CINEMA-SMART are composed of CSPACE, SACAP (Severe Accident ContainmentAnalysis 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 analysis, respectively. The main sequence of the SBO (Station BlackOut) for the SMART was analyzed using CINEMA-SMART computer code. In particular, this analysis is focused on an evaluation of core melt progression, RCS depressurization, and containment thermal hydraulic behavior during a severe accident. The CINEMA results have shown that the integrity of the containment can be maintained during a SBO accident in the SMART.

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