The Model Establishment and Analysis of TRACE/FRAPTRAN for Chinshan Nuclear Power Plant Spent Fuel Pool

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.

Authors:

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

Keywords:

• TRACE
• FRAPTRAN
• SNAP
• spent fuel pool.

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
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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
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[7] J.R. Wang, H.T. Lin, W.W. Li, S.W. Chen, C. Shih, “Application of
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Power Plant”, Applied Mechanics and Materials, Vols. 479-480, pp.
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[8] U.S. NRC, “Standard Review Plan for the Review of Safety Analysis
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