The Analysis and Simulation of TRACE in the Ultimate Response Guideline for Chinshan BWR/4 Nuclear Power Plant
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.
[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.
[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.
@article{"International Journal of Earth, Energy and Environmental Sciences:70115", author = "J. R. Wang and H. T. Lin and H. C. Chen and C. Shih and S. W. Chen and S. C. Chiang and C. C. Liu", title = "The Analysis and Simulation of TRACE in the Ultimate Response Guideline for Chinshan BWR/4 Nuclear Power Plant", 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.", volume = "9", number = "6", pages = "717-5", }