The COSINE-SACM code focuses on the behaviors of reactor core components under the condition of severe accident. The code adopts the best-estimate method and the mechanism models on severe accident phenomena. It is used to simulate an acceleration oxidation of the fuel assembly, core melting and relocation, fission products releasing from fuel assembly, formation phenomena of molten pool and creep rupture of structural components, etc. The code can be applied to the severe accident analysis in the nuclear power plant and the research on the mechanism of severe accident phenomena.
The COSINE-SAST code focuses on the behaviors of reactor containment and its internal components under the condition of severe accident. The code adopts an couple method between thermal hydraulics and fission products transportation. It is used to analyze the severe accident sequences, fission products source term distribution and the influence of the engineering safety feature (ESF) on severe accident progress. The code can simulate the various severe accidents in the coolant loop and reactor containment, including the release and transfer of radioactive fission products, hydrogen generation and combustion, MCCI, etc. The code can be applied to the analyses on severe accident sequences, fission products source term and mitigation measure research on severe accident.