참고문헌
- Longze Li, Yapei Zhang, Wenxi Tian, et al., MAAP5 simulation of the PWR severe accident induced by pressurizer safety valve stuck-open accident, Prog. Nucl. Energy 77 (2014) 141-151. https://doi.org/10.1016/j.pnucene.2014.06.014
- T.L. Schulz, Westinghouse AP1000 advanced passive plant, Nucl. Eng. Des. 236 (2006) 1547-1557. https://doi.org/10.1016/j.nucengdes.2006.03.049
- W.W. Wang, G.H. Su, Z.M. Meng, et al., Analyses of liquid entrainment through ADS-4 in AP1000 during a typical small break LOCA transient, Ann. Nucl. Energy 60 (2013) 195-201. https://doi.org/10.1016/j.anucene.2013.05.006
- Zhaoming Meng, Bo Dong, Laishun Wang, et al., Experimental research of liquid entrainment through ADS-4 in AP1000, Ann. Nucl. Energy 72 (2014) 428-437. https://doi.org/10.1016/j.anucene.2014.06.012
- A.K. Trivedi, C. Allison, A. Khanna, et al., AP1000 station blackout study with and without depressurization using RELAP5/SCDAPSIM, Nucl. Eng. Des. 307 (2016) 299-308. https://doi.org/10.1016/j.nucengdes.2016.07.019
- Muhammad Hashim, Hidekazu Yoshikawa, Takeshi Matsuoka, et al., Application case study of AP1000 automatic depressurization system (ADS) for reliability evaluation by GO-FLOW methodology, Nucl. Eng. Des. 278 (2014) 209-221. https://doi.org/10.1016/j.nucengdes.2014.06.040
- Jun Wang, Wenxi Tian, Yapei Zhang, et al., The development of Module Invessel Degraded severe accident Analysis Code MIDAC and the relevant research for CPR1000 during the station blackout scenario, Prog. Nucl. Energy 76 (2014) 44-54. https://doi.org/10.1016/j.pnucene.2014.05.015
- Jun Wang, Wenxi Tian, Yuqiao Fan, et al., The development of a zirconium oxidation calculating program module for Module In-vessel Degraded Analysis Code MIDAC, Prog. Nucl. Energy 73 (2014) 162-171. https://doi.org/10.1016/j.pnucene.2014.02.006
- Jun Wang, Yuqiao Fan, Yapei Zhang, et al., The development of candling module code in module in-vessel degraded analysis code MIDAC and the relevant calculation for CPR1000 during large-break LOCA, J. Nucl. Eng. Radiat. Sci. 0 (2015) 1-10.
- D. Magallon, Characteristics of corium debris bed generated in large-scale fuel-coolant interaction experiments, Nucl. Eng. Des. 236 (2006) 1998-2009. https://doi.org/10.1016/j.nucengdes.2006.03.038
- Y.P. Zhang, S.Z. Qiu, G.H. Su, et al., Analysis of safety margin of in-vessel retention for AP1000, Nucl. Eng. Des. 240 (2010) 2023-2033. https://doi.org/10.1016/j.nucengdes.2010.04.020
-
Grenville Harrop, Bill P. Poirier, Construction of Westinghouse Ap1000
$^{tm}$ Nuclear Power Plants in China, 2010. ICONE18-30077. - Sheng Zhou, Xiliang Zhang, Nuclear energy development in China: a study of opportunities and challenges, Energy 35 (2010) 4282-4288. https://doi.org/10.1016/j.energy.2009.04.020
- Westinghouse Electric Company, AP1000 Design Control Document, 2010. Revision 17.
- D. Lioce, M. Asztalos, A. Alemberti, et al., AP1000 passive core cooling system pre-operational tests procedure definition and simulation by means of Relap5 Mod.3.3 computer code, Nucl. Eng. Des. 250 (2012) 538-547.
- Wei Li, Xiaoli Wu, Yapei Zhang, et al., Analysis of PWR RPV lower head SBLOCA scenarios with the failure of high-pressure injection system using MAAP5, Prog. Nucl. Energy 77 (2014) 48-64. https://doi.org/10.1016/j.pnucene.2014.06.009
- Anonymous, AP1000 Design Control Document, Revision 17, Westinghouse Electric Company, 2010.
- J. Montero-Mayorga, C. Queral, J. Gonzalez-Cadelo, AP1000(R) SBLOCA simulations with TRACE code, Ann. Nucl. Energy 75 (2015) 87-100. https://doi.org/10.1016/j.anucene.2014.07.045