Application of TRACE and FRAPTRAN 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 and tsunami, the cooling system of the spent fuel pool failed and the safety issue of the spent fuel pool generated. In this study, the safety analysis of the Chinshan NPP spent fuel pool was performed by using TRACE and FRAPTRAN, which also assumed the cooling system of the spent fuel pool failed. There are two cases considered in this study. Case 1 is the no fire water injection in the spent fuel pool. Case 2 is the fire water injection while the water level of the spent fuel pool uncover the length of fuel rods over 1/3 full length. The analysis results of the case 1 show that the failure of cladding occurs in about 3.6 day. However, the results of case 2 indicate that the integrity of cladding is kept after the fire water injection.

• Periodical: Applied Mechanics and Materials (Volumes 479-480)
• Pages: 543-547
• DOI: https://doi.org/10.4028/www.scientific.net/AMM.479-480.543
• Online since: December 2013
• Authors: Jong Rong Wang, Hao Tzu Lin, Wan Yun Li, Shao Wen Chen, Chun Kuan Shih
• Keywords: BWR, FRAPTRAN, Spent Fuel Pool, Trace

References

[1] U.S. NRC, TRACE V5. 0 Theory Manual, Division of Safety Analysis, Office of Nuclear Regulatory Research (2010).

[2] K.J. Geelhood, W.G. Luscher, C.E. Beyer, J.M. Cuta, FRAPTRAN 1. 4: A Computer Code for the Transient Analysis of Oxide Fuel Rods, NUREG/CR-7023, Vol. 1, PNNL-19400, Vol. 1, , USA (2010).

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

[4] U.S. NRC, 10CFR50. 46c, ML110970044 (2011).