Analysis of Kuosheng Station Blackout accident using MELCOR 1.8.4

The MELCOR code, developed by Sandia National Laboratories, is a fully inte grated, relatively fast-running code that models the progression of severe accidents in commercial light water nuclear power plants (NPPs). A specific station blackout (SBO) accident for Kuosheng (BWR-6) NPP is simu lated using the MELCOR 1.8.4 code. The MELCOR input deck for Kuosheng NPP i s established based on Kuosheng NPP design data and the MELCOR users' guide s. The initial steady-state conditions are generated with a developed self- initialization algorithm. The main severe accident phenomena and the fissio n product release functions associated with the SBO accident were simulated . The predicted results are plausible and as expected in light of current u nderstanding of severe accident phenomena. The uncertainty of this analysis is briefly discussed The important features of the MELCOR 1.8.4 are descri bed. The estimated results provide useful information for the probabilistic risk assessment (PRA) of Kuosheng NPP. This tool will be applied to the PR A, the severe accident analysis, and the severe accident management study o f Kuosheng NPP in the near future.