Abstract
The Unit 1 of Kuosheng nuclear power plant is in the decommissioning transition phase and still has spent fuel in the core of reactor now. The time to reach the TAF (top of active fuel) for water level and reach 600/800 °C for cladding temperature are the key parameters in the safety analysis, these affect that the plant has how much time to handle transients. Therefore, to study the water level and cladding temperature for station blackout (SBO) and loss of coolant accident (LOCA) transients in the decommissioning transition phase, the analysis model of Kuosheng nuclear power plant was established by using TRACE code. To evaluate the effect of the decay heat of spent fuel on the water level and cladding temperature, the sensitivity analysis of decay heat was also performed in this study.
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: None declared.
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Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
References
Applied Programming Technology (2012). Symbolic nuclear analysis package (SNAP) user’s manual. Applied Programming Technology, Inc, Bloomsburg, PA.Search in Google Scholar
Carlos, S., Sanchez-Saez, F., and Martorell, S. (2014). Use of TRACE best estimate code to analyze spent fuel storage pools safety. Prog. Nucl. Energy 77: 224–238, https://doi.org/10.1016/j.pnucene.2014.07.008.Search in Google Scholar
Collins, T.E. and Hubbard, G. (2001). Technical study of spent fuel pool accident risk at decommissioning nuclear power plants. NUREG-1738. U.S. NRC, Washington, DC.Search in Google Scholar
Machiels, A., Cheng, B., Kessler, J., Rahn, F., Yang, R., Edsinger, K., and Carter, B. (2012). Summary of the EPRI early event analysis of the Fukushima Daiichi spent fuel pools following the March 11, 2011 earthquake and tsunami in Japan. EPRI TR-1025058, USA.Search in Google Scholar
Taiwan Power Company (2001). Final safety analysis report for Kousheng nuclear power station units 1&2 (FSAR). Taiwan Power Company, Taipei.Search in Google Scholar
Tsukamoto, N. (2019). Study on modeling of spray cooling for spent fuel pool accidents. J. Nucl. Sci. Technol. 56: 945–952, https://doi.org/10.1080/00223131.2019.1626778.Search in Google Scholar
U.S. NRC (1981). Residual decay energy for light-water reactors for long-term cooling. U.S. NRC, Washington, DC.Search in Google Scholar
U.S. NRC (2014). TRACE V5.840 user’s manual. U.S. NRC, Washington, DC.Search in Google Scholar
U.S. NRC (2017). TRACE theory manual V5.0 P5 field equations, solution methods and physical models. U.S. NRC, Washington, DC.Search in Google Scholar
Xiao, B.B. and Hsia, C.Y. (2022). The thermal analysis of pre-defueled operation for decommissioning of a BWR4 reactor. Ann. Nucl. Energy 167: 108804, https://doi.org/10.1016/j.anucene.2021.108804.Search in Google Scholar
Zhang, Z.W., Du, Y., Liang, T.H., Chou, L.Y., and Liang, K.S. (2018). Safety evaluation of an extended refilling mode operation after the permanent shutdown of a BWR/4 reactor. Ann. Nucl. Energy 120: 89–99, https://doi.org/10.1016/j.anucene.2018.05.032.Search in Google Scholar
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