System Response Analysis of Rod Ejection Accident for OPR1000 Using Korea Non-LOCA Analysis Package

Korea Electric Power Research Institute (KEPRI) of Korea Electric Power Corporation (KEPCO) has been developed the non-loss-of-coolant accident (non-LOCA) analysis methodology, called as the Korea Non-LOCA Analysis Package (KNAP), for the typical Optimized Power Reactor 1000 (OPR1000) plants. The RETRAN hot spot model (HSM) of KNAP has been contrived to replace the functions of STRIKIN-II code of ABB-CE, which is used for the rod ejection accident (REA) analysis. The HSM could be used to estimate the fuel temperature, fuel enthalpy, cladding surface temperature, etc., which are used to confirm the safety limits of REA. In this work, to estimate the feasibility of HSM, the typical cases of REA were analyzed and the results were compared with those calculated by the CESEC-III and STRIKIN-II, which were used to prepared the final safety analysis report (FSAR) of Ul-Chin Units 3 and 4 (UCN-3/4). Through the study, it was concluded that the HSM of KNAP showed the acceptable results