H. Shiroyama, “Regulatory failures of nuclear safety in Japan –the case of Fukushima accident,” in: Proc. of the Earth System Governance Tokyo Conference: Complex Architectures, Multiple Agents, Earth System Governance, Tokyo, Japan, January 2013.
 T. Yonomoto, Y. Anoda, Y. Kukita, and Y. Peng, “CCFL characteristicsof PWR steam generator U-tubes,” in: Proc. of the ANS International Topical Meeting on Safety of Thermal Reactors, American Nuclear Society, Portland, Ore, USA, July 1991.
 S. Al Issa and R. Macian-Juan, “A review of CCFL phenomenon,” Ann. Nucl. Energy, vol. 38, 2011, pp. 1795–1819.
 T. Kusunoki, T. Nozue, K. Hayashi, S. Hosokawa, A. Tomiyama, and M. Murase, “Condensation experiments for counter-current flow limitation in an inverted U-tube,” J. Nucl. Sci. Technol., vol. 53, 2016, pp. 486–495.
 The ROSA-V Group, “ROSA-V Large Scale Test Facility (LSTF) System Description for the Third and Fourth Simulated Fuel Assemblies,” JAERI-Tech 2003-037, Japan Atomic Energy Research Institute, Ibaraki, Japan, 2003.
 T. Takeda, H. Asaka, and H. Nakamura, “Analysis of the OECD/NEA ROSA project experiment simulating a PWR small break LOCA with high-power natural circulation,” Ann. Nucl. Energy, vol. 36, 2009, pp. 386–392.
 T. Takeda, “Uncertainty analysis of ROSA/LSTF test on pressurized water reactor cold leg small-break loss-of-coolant accident without scram,” Int. J. Nucl. Quantum Eng., vol. 13, 2019, pp. 82–90.
 T. Takeda, H. Asaka, and H. Nakamura, “RELAP5 analysis of OECD/NEA ROSA project experiment simulating a PWR loss-of-feedwater transient with high-power natural circulation,” Sci. Technol. Nucl. Installations, Article ID 957285, vol. 2012, 2012, pp. 1–15.
 G.G. Loomis and K. Soda, “Results of the Semiscale Mod-2A natural circulation experiments,” USNRC Report NUREG/CR-2335, EGG-2200, Idaho National Engineering Laboratory, 1982.
 F. D’Auria and G.M. Galassi, “Characterization of instabilities during two-phase natural circulation in PWR typical conditions,” Exper. Therm. Fluid Sci., vol. 3, 1990, pp. 641–650.
 P. Basin, R. Deruaz, T. Yonomoto, and Y. Kukita, “BETHSY/LSTF counterpart test on natural circulation in a pressurized water reactor,” in: Proc. of the 1992 National Heat Transfer Conference, San Diego, CA, USA, August 1992.
 Y.M. Ferng and C.H. Lee, “Numerical simulation of natural circulation experiments conducted at the IIST facility,” Nucl. Eng. Des., vol. 148, 1994, pp. 119–128.
 M. Cherubini, W. Giannotti, D. Araneo, and F. D’Auria, “Use of the natural circulation flow map for natural circulation systems evaluation,” Sci. Technol. Nucl. Installations, Article ID 479673, vol. 2008, 2008, pp. 1–7.
 A. Del Nevo, F. D’Auria, M. Mazzini, M. Bykov, I.V. Elkin, and A. Suslov, “The design of PSB-VVER experiments relevant to accident management,” J. Power Energy Syst., vol. 2, 2008, pp. 371–385.
 K. Umminger, L. Dennhardt, S. Schollenberger, and B. Schoen, “Integral Test Facility PKL: Experimental PWR Accident Investigation,” Sci. Technol. Nucl. Installations, Article ID 891056, vol. 2012, 2012, pp. 1–16.
 V. Kouhia, V. Riikonen, O.P. Kauppinen, et al., “Benchmark exercise on SBLOCA experiment of PWR PACTEL facility,” Ann. Nucl. Energy, vol. 59, 2013, pp. 149–156.
 J. Kim, K.Y. Choi, K.H. Kang, Y. Park, B.U. Bae, and C.H. Song, “Experimental study for natural circulation flow regime map of ATLAS,” Transaction of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 2014.
 Y. Kukita, H. Nakamura, K. Tasaka, and C. Chauliac, “Nonuniform steam generator U-tube flow distribution during natural circulation tests in ROSA-IV large scale test facility,” Nucl. Sci. Eng., vol. 99, 1988, pp. 289–298.
 K. Tasaka, Y. Kukita, Y. Koizumi, M. Osakabe, and H. Nakamura, “The results of 5% small-break LOCA tests and natural circulation tests at the ROSA-IV LSTF,” Nucl. Eng. Des., vol. 108, 1988, pp. 37–44.
 F. D’Auria and M. Frogheri, “Use of a natural circulation map for assessing PWR performance,” Nucl. Eng. Des., vol. 215, 2002, pp. 111–126.
 N. Aksan, F. D’Auria, H. Glaeser, R. Pochard, C. Richards, and A. Sjoberg, “Separate Effects Test Matrix for Thermal-Hydraulic Code Validation – Volume I: Phenomena Characterisation and Selection of Facilities and Tests,” CSNI report OECD/GD(94)82, 1994.
 N. Aksan, F. D’Auria, H. Glaeser, J. Lillington, R. Pochard, and A. Sjoberg, “Evaluation of the CSNI Separate Effects Tests (SET) Validation Matrix,” CSNI report OECD/GD(97)9, 1996.
 USNRC Nuclear Safety Analysis Division, “RELAP5/MOD3.3 Code Manual,” NUREG/CR-5535/Rev 1, Information Systems Laboratories, Inc., 2001.
 D. Bestion, F. D’Auria, P. Lien, and H. Nakamura, “A state-of-the-art report on scaling in system thermal-hydraulics applications to nuclear reactor safety,” NEA/CSNI/R(2016)14, 2017.
 N. Zuber, “Problems in Modeling Small Break LOCA,” NUREG-0724, USNRC, Washington, DC, 1980.
 G.B. Wallis, “One-Dimensional Two-Phase Flow,” McGraw-Hill Book, New York, USA, 1969.