An experimental study of CHF and power transients in flow boiling at low-pressure low-flow conditions

References

• P. Goel, A. K. Nayak, P. Ghosh, and J. B. Joshi, “Experimental study of bubble departure characteristics in forced convective subcooled nucleate boiling,” Exp. Heat Transf., vol. 31, pp. 194–218, 2018. DOI: 10.1080/08916152.2017.1397821.
   Web of Science ®Google Scholar
• J. C. M. Leung, Occurrence of Critical Heat Flux during Blowdown with Flow Reversal. IL (United States): [LWR], Argonne, 1976.
   Google Scholar
• K. Mishima and M. Ishii, Critical Heat-Flux Experiments under Low-Flow Conditions in a Vertical Annulus. IL (United States): [PWR; BWR; LMFBR], Argonne, 1982.
   Google Scholar
• C. Park, S. Heung Chang, and W.-P. Baek, “Critical heat flux for finned and unfinned geometries under low flow and low pressure conditions,” Nucl. Eng. Des., vol. 183, pp. 235–247, 1998. DOI: 10.1016/S0029-5493(98)00170-8.
   Web of Science ®Google Scholar
• M. Kaichiro, N. Hiedeaki, and M. Itaru, “Boiling burnout and flow instabilities for water flowing in a round tube under atmospheric pressure,” Int. J. Heat Mass Transf., vol. 28, pp. 1115–1129, 1985. DOI: 10.1016/0017-9310(85)90120-6.
   Web of Science ®Google Scholar
• K. Mishima and H. Nishihara, “Effect of channel geometry on critical heat flux for low pressure water,” Int. J. Heat Mass Transf., vol. 30, pp. 1169–1182, 1987. DOI: 10.1016/0017-9310(87)90046-9.
   Web of Science ®Google Scholar
• M. S. El-Genk, S. J. Haynes, and K. Sung-Ho, “Experimental studies of critical heat flux for low flow of water in vertical annuli at near atmospheric pressure,” Int. J. Heat Mass Transf., vol. 31, pp. 2291–2304, 1988. DOI: 10.1016/0017-9310(88)90161-5.
   Web of Science ®Google Scholar
• S. H. Chang, W.-P. Baek, and T. M. Bae, “A study of critical heat flux for low flow of water in vertical round tubes under low pressure,” Nucl. Eng. Des., vol. 132, pp. 225–237, 1991. DOI: 10.1016/0029-5493(91)90267-L.
   Web of Science ®Google Scholar
• C. H. Oh and S. B. Englert, “Critical heat flux for low flow boiling in vertical uniformly heated thin rectangular channels,” Int. J. Heat Mass Transf., vol. 36, pp. 325–335, 1993. DOI: 10.1016/0017-9310(93)80008-I.
   Web of Science ®Google Scholar
• J. Park, W. Baek, and S. Chang, “Critical heat flux and flow pattern for water flow in annular geometry,” Nucl. Eng. Des., vol. 172, pp. 137–155, 1997. DOI: 10.1016/S0029-5493(97)00032-0.
   Web of Science ®Google Scholar
• T. Schoesse, et al., “Critical heat flux in a vertical annulus under low upward flow and near atmospheric pressure,” J. Nucl. Sci. Technol., vol. 34, pp. 559–570, 1997. DOI: 10.1080/18811248.1997.9733709.
   Web of Science ®Google Scholar
• S. Y. Chun, et al., “Critical heat flux under zero flow conditions in vertical annulus with uniformly and non-uniformly heated sections,” Nucl. Eng. Des., vol. 205, pp. 265–279, 2001. DOI: 10.1016/S0029-5493(00)00377-0.
   Web of Science ®Google Scholar
• C. Haas, T. Schulenberg, and T. Wetzel, “Critical heat flux for flow boiling of water at low pressure in vertical internally heated annuli,” Int. J. Heat Mass Transf., vol. 60, pp. 380–391, 2013. DOI: 10.1016/j.ijheatmasstransfer.2012.12.038.
   Web of Science ®Google Scholar
• G. Mayer, R. Nagy, and I. Nagy, “An experimental study on critical heat flux in vertical annulus under low flow and low pressure conditions,” Nucl. Eng. Des., vol. 310, pp. 461–469, 2016. DOI: 10.1016/j.nucengdes.2016.10.026.
   Web of Science ®Google Scholar
• S. H. Chang, K. W. Lee, and D. C. Groeneveld, “Transient-effects modeling of critical heat flux,” Nucl. Eng. Des., vol. 113, pp. 51–57, 1989. DOI: 10.1016/0029-5493(89)90295-1.
   Web of Science ®Google Scholar
• G. P. Celata and M. Cumo, “CHF during flow rate, pressure and power transients in heated channels,” Transient Phenomena in Multiphase Flow International Seminar, Dubrovnik, Yugoslavia, 1987. 24–29.
   Google Scholar
• A. Dasgupta, et al., “Experimental investigation on dominant waves in upward air-water two-phase flow in churn and annular regime,” Exp. Therm. Fluid Sci., vol. 81, pp. 147–163, 2017. DOI: 10.1016/j.expthermflusci.2016.10.012.
   Web of Science ®Google Scholar
• W. H. Lowdermilk, C. D. Lanzo, and B. L. Siegel, Investigation of Boiling Burnout and Flow Stability for Water Flowing in Tubes: NACA TN 4382, National Advisory Committee for Aeronautics, Washington, DC, 1958.
   Google Scholar
• P. Griffith, J. F. Pearson, and R. J. Lepkowski, “Critical heat flux during a loss-of-coolant accident,” Nucl. Saf., vol. 18, pp. 298–305, 1977.
   Google Scholar
• D. C. Groeneveld, et al., “The 2006 CHF look-up table,” Nucl. Eng. Des., vol. 237, pp. 1909–1922, 2007. DOI: 10.1016/j.nucengdes.2007.02.014.
   Web of Science ®Google Scholar