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

Author:

Wang Jong Rong1,Lin Hao Tzu1,Tseng Yung Shin1,Shih Chun Kuan2

Affiliation:

1. Institute of Nuclear Energy Research

2. National Tsing Hua University

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.

Publisher

Trans Tech Publications, Ltd.

Reference5 articles.

1. U.S. NRC, in: TRACE V5. 0 Theory Manual, edited by Division of Safety Analysis, Office of Nuclear Regulatory Research (2010).

2. ANSYS Inc., in: ANSYS, FLUENT V12. 0 User's Manual, edited by ANSYS Inc. (2009).

3. AREVA NP Inc., in: Startup and Operations Report Chinshan Unit 1 Cycle 24, edited by AREVA NP Inc., ANP-2772(P) Revision 0 (2008).

4. ANSYS Inc., in: ANSYS, User Defined Function Manual, edited by ANSYS Inc. (2009).

5. Y. S. Tseng, et al., in: Analysis of Alternative Shutdown Cooling for Chinshan Nuclear Power Plant Using CFD Simulation, INER report, INER-7700 (2010).

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