The Analysis of TRACE/FRAPTRAN in the Fuel Rods of Maanshan PWR for LBLOCA

Fuel rod analysis program transient (FRAPTRAN) 
code was used to study the fuel rod performance during a postulated 
large break loss of coolant accident (LBLOCA) in Maanshan nuclear 
power plant (NPP). 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 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.

• J. R. Wang
• W.Y. Li
• H.T. Lin
• J.H. Yang
• C. Shih
• S.W. Chen

• —FRAPTRAN
• TRACE
• LOCA
• PWR.

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