Abstract
In this paper, the Fuel Rod Analysis Program Transient (FRAPTRAN) code and SNAP program, a graphic user interface program, were used to study the fuel rod transient performance during a postulated Large Break Loss of Coolant Accident (LBLOCA) in Maanshan nuclear power plant. Previous transient results from thermal hydraulic code, TRACE, with the same LBLOCA scenario, were used as input boundary conditions for FRAPTRAN. The simulation results showed that the peak cladding temperatures at six zones and the fuel centerline temperatures were all below the 10CFR50.46 LOCA criteria. In addition, the maximum hoop stress was 18 MPa and the oxide thickness was 0.003mm for the present simulation cases, which are all within the safety operation ranges. The present study confirms that this analysis method, the FRAPTRAN code combined with TRACE, is an appropriate approach to predict the fuel integrity under LBLOCA with operational ECCS.