The Analysis and Simulation of TRACE in the Ultimate Response Guideline for Chinshan BWR/4 Nuclear Power Plant

Authors: J. R. Wang, H. T. Lin, H. C. Chen, C. Shih, S. W. Chen, S. C. Chiang, C. C. Liu

Abstract:

In this research, TRACE model of Chinshan BWR/4 nuclear power plant (NPP) has been developed for the simulation and analysis of ultimate response guideline (URG).The main actions of URG are the depressurization and low pressure water injection of reactor and containment venting. This research focuses to verify the URG efficiency under Fukushima-like conditions. TRACE analysis results show that the URG can keep the PCT below the criteria 1088.7 K under Fukushima-like conditions. It indicated that Chinshan NPP was safe.

Keywords: BWR, TRACE, safety analysis, URG.

Digital Object Identifier (DOI): doi.org/10.5281/zenodo.1106983

References:

[1] K.S. Liang, S.C. Chiang, Y.F. Hsu, H.J. Young, B.S. Pei, L.C. Wang, “The ultimate emergency measures to secure a NPP under an accidental condition with no designed power or water supply,” Nuclear Engineering and Design, 253, pp.259-268,2012.
[2] U.S. NRC, “TRACE V5.0 User’s Manual”, 2010.
[3] J. R. Wang, H. T. Lin, Y. H. Cheng, W. C. Wang, C. Shih, “TRACE modeling and its verification using Maanshan PWR start-up tests”, Annals of Nuclear Energy, 36, pp. 527-536, 2009.
[4] C. H. Chen, J. R. Wang, H. T. Lin, C. Shih, “ATWS analysis for Maanshan PWR using TRACE/SNAP code”, Annals of Nuclear Energy, 72, pp. 1-10, 2014.
[5] H. T. Lin, J. R. Wang, C. Shih, “The development and assessment of TRACE model for Lungmen ABWR”, Kerntechnik, 76, pp. 205-215, 2011.
[6] H. T. Lin, J. R. Wang, H. C. Chen, C. Shih, “The development and assessment of TRACE/PARCS model for Lungmen ABWR”, Nuclear Engineering and Design, 273, pp. 241-250, 2014.
[7] C. Y. Chen, C. Shih, J. R. Wang, H. T. Lin, “Sensitivity study on the counter-current flow limitation in the DEGLBLOCA with the TRACE code”, Annals of Nuclear Energy, 57,pp. 121-129, 2013.
[8] C. Y. Chen, C. Shih, J. R. Wang, “The alternate mitigation strategies on the extreme event of the LOCA and the SBO with the TRACE Chinshan BWR4 model”, Nuclear Engineering and Design, 256, pp. 332-340, 2013.
[9] J. H. Lee, J. R. Wang, H. T. Lin, S. M. Yang, C. Shih, “TRACE modeling of Chinshan load rejection startup test”, American Nuclear Society: 2009 Annual Meeting.
[10] Taiwan Power Company, “Final Safety Analysis Report for Chinshan Nuclear Power Station Units 1&2”, 1999.
[11] W. S. Hsu, J. R. Tang, “The calculation notes of the startup test benchmark analysis for the Chinshan RETRAN-02 model”, INER report, 1997.