Commenced in January 2007
Frequency: Monthly
Edition: International
Paper Count: 30121
The Model Establishment and Analysis of TRACE/FRAPTRAN for Chinshan Nuclear Power Plant Spent Fuel Pool

Authors: J. R. Wang, H. T. Lin, Y. S. Tseng, W. Y. Li, H. C. Chen, S. W. Chen, C. Shih

Abstract:

TRACE is developed by U.S. NRC for the nuclear power plants (NPPs) safety analysis. We focus on the establishment and application of TRACE/FRAPTRAN/SNAP models for Chinshan NPP (BWR/4) spent fuel pool in this research. The geometry is 12.17 m × 7.87 m × 11.61 m for the spent fuel pool. In this study, there are three TRACE/SNAP models: one-channel, two-channel, and multi-channel TRACE/SNAP model. Additionally, the cooling system failure of the spent fuel pool was simulated and analyzed by using the above models. According to the analysis results, the peak cladding temperature response was more accurate in the multi-channel TRACE/SNAP model. The results depicted that the uncovered of the fuels occurred at 2.7 day after the cooling system failed. In order to estimate the detailed fuel rods performance, FRAPTRAN code was used in this research. According to the results of FRAPTRAN, the highest cladding temperature located on the node 21 of the fuel rod (the highest node at node 23) and the cladding burst roughly after 3.7 day.

Keywords: TRACE, FRAPTRAN, SNAP, spent fuel pool.

Digital Object Identifier (DOI): doi.org/10.5281/zenodo.1124613

Procedia APA BibTeX Chicago EndNote Harvard JSON MLA RIS XML ISO 690 PDF Downloads 998

References:


[1] Taiwan Power Company, “Final Safety Analysis Report for Chinshan Nuclear Power Station Units 1&2”, 1999.
[2] U.S. NRC, “TRACE V5.0 User’s Manual”, 2010.
[3] 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, 2010.
[4] Applied Programming Technology, Inc., “Symbolic nuclear analysis package (SNAP) user's manual”, 2012.
[5] J.R. Wang, H.T. Lin, Y.S. Tseng, C. Shih, “Application of TRACE and CFD in the spent fuel pool of Chinshan nuclear power plant”, Applied Mechanics and Materials Vol. 145, pp. 78-82, 2012.
[6] J.R. Wang, H.T. Lin, W.W. Li, H.C. Chen, C. Shih, “The Spent Fuel Pool Analysis Of Chinshan Nuclear Power Plant By Using TRACE/FRAPCON-3.4”, Advanced Materials Research, Vols. 690-693, pp. 2947-2950, 2013.
[7] J.R. Wang, H.T. Lin, W.W. Li, S.W. Chen, C. Shih, “Application of TRACE and FRAPTRAN in the Spent Fuel Pool of Chinshan Nuclear Power Plant”, Applied Mechanics and Materials, Vols. 479-480, pp. 543-547, 2014.
[8] U.S. NRC, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition-Auxiliary Systems”, NUREG-0800, Chapter 9, 2007.