References
- Schulz TL. Westinghouse AP1000 advanced passive plant. Nucl Eng Des. 2006 Aug;236:1547–1557.
- Yan W, Xie H. Prospect on the LOCA analysis method on the advanced pressurized water reactor in China, In: Guanghui Su, Liangzhi Cao, Yassin A Hassan, editors. 18th International Conference on Nuclear Engineering, 2010 May 17-21, Xi'an, China, USA: ASME; 2010. p. 377–382.
- Sang IL, Hee CNO. Gravity-driven injection experiments and direct-contact condensation regime map for passive high-pressure injection system. Nucl Eng Des. 1998 Jul;183:213–234.
- Ji FY, Li CL, Zheng H, et al. Study of core make-up water experiment of AC600 make-up water tank. Nucl Power Eng. 1999 Apr;20:52–56. Chinese.
- Peng YK. Effect of initial condition on temperature distribution and steam condensation behavior during CMT drainage [dissertation]. Chongqing University; Chongqing, China, 2003. Chinese.
- Liao L, Zhou QF. CMT injection analysis on loss of normal feedwater flow accident ATWS of AP1000 NPP. Atom Energ Sci Technol. 2011 Dec;45:1462–1465.
- Wang M, Tian W, Qiu S, et al. An evaluation of designed passive core makeup tank (CMT) for China pressurized reactor. Ann Nucl Energy. 2013 Jun;56:81–86.
- Yonomoto T, Kukita Y, Anoda Y. Passive safety injection experiments with a large-scale pressurized water reactor simulator. Nucl Technol. 1995 Mar;109:338–345.
- Yonomoto T, Kondo M, Kukita Y, et al. Core makeup tank behavior observed during the ROSA-AP600 experiments. Nucl Technol. 1997 Aug;119:112–122.
- Friend MT, Wright RF, Hundal R, et al. Simulated AP600 response to small-break loss-of-coolant-accident and non-loss-of coolant accident events: analysis of SPES-2 integral test results. Nucl Technol. 1998;122:19–42.
- Wright RF. Simulated AP1000 response to design basis small-break LOCA events in APEX-1000 test facility. Nucl Eng Technol. 2007 Aug;39:287–298.
- Reyes JN, Hochreiter LE. Scaling analysis for the OSU AP600 test facility (APEX). Nucl Eng Des. 1998 Nov;186:53–109.
- Deng CC, Chang HJ, Qin BK, et al. CMT scaling analysis and distortion evaluation in passive integral test facility. Atom Energ Sci Technol. 2013 Nov;47:2027–2035. Chinese.
- Zuber N, Wilson GE, Ishii M, et al. An integrated structure and scaling methodology for severe accident technical resolution: development of methodology. Nucl Eng Des. 1998 Nov;186:1–21.
- Reyes JN. The dynamical system scaling methodology. The 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), 2015 Aug. 30-Sep, Chicago, IL; USA: ANS. 2015.