Application of TRACE and CFD in the Spent Fuel Pool of Chinshan Nuclear Power Plant

Abstract

In the nuclear power plant (NPP) safety, the safety analysis of the NPP is very important work. In Fukushima NPP event, due to the earthquake, the cooling system of the spent fuel pool failed and the safety issue of the spent fuel pool generated. After Fukushima NPP event, INER (Institute of Nuclear Energy Research, Atomic Energy Council, R.O.C.) performed the safety analysis of the spent fuel pool for Chinshan NPP which also assumed the cooling system of the spent fuel pool failed. The geometry of the Chinshan NPP spent fuel pool is 12.17 m × 7.87 m × 11.61 m and the initial condition is 60 ¢J / 1.013 × 105 Pa. In general, the NPP safety analysis is performed by the thermal hydraulic codes. The advanced thermal hydraulic code named TRACE for the NPP safety analysis is developing by U.S. NRC. Therefore, the safety analysis of the spent fuel pool for Chinshan NPP is performed by TRACE. Besides, this safety analysis is also performed by CFD. The analysis result of TRACE and CFD are similar. The results show that the uncovered of the fuels occur in 2.7 days and the metal-water reaction of the fuels occur in 3.5 days after the cooling system failed.

The Spent Fuel Pool Analysis of Chinshan Nuclear Power Plant by Using TRACE/FRAPCON-3.4

“…Besides, the top of fuel rod contains springs. Second, this study used TRACE analysis results as boundary condition to calculate the cladding performance by FRAPCON-3.4 under the cooling system failed of spent fuel poor for Chinshan NPP [4]. The TRACE model of the Chinshan NPP spent fuel pool is 12.17 m × 7.87 m × 11.61 m and the initial condition is 60 ℃ / 1.013 × 10 5 Pa.…”

“…The second step is the application of FRAPCON-3.4 in the spent fuel pool of Chinshan NPP. By using the TRACE analysis results as the input data of FRAPCON-3.4 [4], FRAPCON-3.4 can calculate the temperature, hoop stress, oxide thickness of cladding in spent fuel pool.…”

Use of TRACE best estimate code to analyze spent fuel storage pools safety

“…In this work a model for RELAP-5 to simulate the spent fuel pools is used to analyze the evolution of water evaporation and spent fuel uncovering. Finally, in (Wang et al , 2012), the loss of cooling in Chinshan nuclear power plant is simulated using FLUENT and TRACE codes.…”

Features of modelling of processes in spent fuel pools using various system codes

“…The Tehran research reactor (TRR) make-up water system was investigated in their work. Assuming the loss of cooling system for the SFP located at the Chinshan NPP in Taiwan, Wang et al (2012) adopted the TRACE code coupled with the CFD method to study the safety issue related to the SFP. Their results showed that the fuel uncover may occur about 2.7 days after the loss of cooling system in the SFP.…”