Abstract
Abstract As specified in the 10 CFR 50.46 of U.S Nuclear Regulatory Commission, lisensing calculations of Loss of Coolant Accident (LOCA) of Light Water Reactor can be performed by the conservative method or the realistic method. In the present study, the conservative method is adopted to analyze the large break LOCA accident of Kuosheng Nuclear Power Plant of Taiwan Power Company. The plant emolys a Boiling Water Reactor (BWR VI) designed by General Electric.. Based on RELAP5-3D input deck of the plant analyzed, a LOCA Evaluation Model input deck for RELAP5-3DK is developed. The results of the analyses are compared with the results of the fuel supplier of the plant. The major chracteristics of LOCA alalyses of the present study are:(1) double-ended large break at recirculation suction side, (2) 104.2% rated thermal power & 75% core flow, (3) top-peak axial power distribution, (4) failure of high pressure spray system is chosen as the single failure of emergency core cooling system. Sensitivity study of initial condition is also performed. The combination used in the analysis is high reactor vessel pressure、low reactor vessel water level at L-3、low feedwater temperature. It has been identified the most conservative estimation of the peak cladding temperature (PCT) is 1844 ℉。