Abstract
The Korea Electric Power Research Institute has developed the non-loss-of-coolant accident analysis methodology, KNAP, for the typical Optimized Power Reactor 1000 and Advanced Power Reactor 1400 in Korea. The RETRAN hot spot model (HSM) has been developed to replace the functions of STRIKIN-II code of ABB-CE. To estimate the feasibility of HSM, the typical cases of rod ejection accidents (REA) were analyzed and the results were compared with those mentioned in Final Safety Analysis Report of Ul-chin Units 3 & 4 or Standard Safety Analysis Report of APR1400. Through this study, it was concluded that the HSM of KNAP could be applicable to the object plants from the viewpoint of REA.
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