REFERENCES
- Merilo, M., Critical Heat Flux Experiments in a Vertical and Horizontal Tube With Both Freon-12 and Water as Coolant, Nuclear Engineering and Design, vol. 44, pp. 1–16, 1977.
- Merilo, M., Fluid-To-Fluid Modeling and Correlation of Flow Boiling Crisis in Horizontal Tubes, International Journal of Multiphase Flow, vol. 5, pp. 313–325, 1979.
- Yu, W., France, D.M., Wambsganss, M.W., and Hull, J.R., Two Phase Pressure Drop, Boiling Heat Transfer and Critical Heat Flux to Water in a Small Diameter Horizontal Tube, International Journal of Multiphase Flow, vol. 36, pp. 927–941, 2002.
- Groeneveld, D.C., Shan, J.Q., Vasić, A.Z., Leung, L.K. H., Durmayaz, A., Yang, J., Cheng, S.C., and Tanase, A., The 2006 CHF Look-Up Table, Nuclear Engineering and Design, vol. 237, pp. 1909–1922, 2007.
- Kim, H.C., Baek, W.P., and Chang, S.H., Critical Heat Flux of Water in Vertical Round Tubes at Low Pressure and Low Flow Conditions, Nuclear Engineering and Design, vol. 36, pp. 49–73, 2000.
- Mishima, K., and Ishii, M., Flow Regime Transition Criteria for Upward Two-Phase Flow in Vertical Tubes, International Journal of Heat and Mass Transfer, vol. 27, no. 5, pp. 723–737, 1984.
- Shah, M.M., Improved General Correlation for Critical Heat Flux During Upflow in Uniformly Heated Vertical Tubes, International Journal of Heat and Fluid Flow, vol. 8, no. 4, pp. 326–335, 1987.
- Kim, H.C., Baek, W.P., and Chang, S.H., Critical Heat Flux of Water in Vertical Round Tubes at Low Pressure and Low Conditions, Nuclear Engineering and Design, vol. 199, nos. 1–2, pp. 49–73, 2000.
- Mishima, K., and Nishihara, H., Boiling Burnout and Flow Instabilities for Water Flowing in a Round Tube Under Atmospheric Pressure, International Journal of Heat and Mass Transfer, vol. 28, no. 6, pp. 1115–1129, 1985.
- Chandraker, D.K., Vijayan, P.K., Saha, D., and Sinha, R.K., Investigation on the Characteristic of CHF in Various Flow Pattern Regimes Based on Look-Up Table Data, Nuclear Engineering Design, vol. 238, pp. 170–177, 2008.
- Wong, Y.L., Groeneveld, D.C., and Cheng, S.C., CHF Prediction for Horizontal Tubes, International Journal of Multiphase Flow, vol. 16, pp. 123–138, 1990.
- Pioro, I.L., Groeneveld, D.C., Leung, L.K. H., Doerffer, S.S., Cheng, S.C., Antoshko, Y.V., Guo, Y., and Vasi, A., Comparison of CHF Measurements in Horizontal and Vertical Tubes Cooled With R-134a, International Journal of Heat and Mass Transfer, vol. 45, pp. 4435–4450, 2002.
- Chen, C.N., Han, J.T., Jen, T.C., Shao, L., and Chen, W.W., Fluid-to-Fluid Modeling of Two-Phase Flow Critical Heat Flux in Horizontal Helically Coiled Tubes, Nuclear Engineering and Design, vol. 241, pp. 1430–1437, 2011.
- Yun, R., and Kim, Y., Critical Quality Prediction for Saturated Flow Boiling of CO2 in Horizontal Small Diameter Tubes, International Journal of Heat and Mass Transfer, vol. 46, pp. 2527–2535, 2003.
- Groeneveld, D.C., Anomalies and Other Concerns Related to the Critical Heat Flux, Nuclear Engineering and Design, vol. 241, pp. 4604–4611, 2011.
- Prabhul, K., Baburajan, P.K., Gupta, S.K., and Prabhu, S.V., Experimental Investigation on Critical Heat Flux in Horizontal Channel for Low Pressure Low Flow (LPLF) Condition, Annals of Nuclear Energy, vol. 37, no. 11, pp. 1467–1475, 2010.
- Moffat, R.J., Describing the Uncertainities in Experimental Results, Experimental Thermal and Fluid Sciences, vol. 1, pp. 3–17, 1988.
- Taitel, Y., and Dukler, A.E., A Model for Predicting Flow Regime Transitions in Horizontal and Near Horizontal Gas–Liquid Flow, AIChE Journal, vol. 22, No. 1, pp. 47–54, 1976.
- RELAP5 Code Development Team, RELAP5/MOD3.2 Code Manual, Vol. I: Code Structure, System Models and Solution Methods, NUREG/CR-5535, Scientech, Inc., Idaho Falls, ID, 1995.
- Tanase, A., Cheng, S.C., Groeneveld, D.C., and Shan, J.Q., Diameter Effect on Critical Heat Flux, Nuclear Engineering and Design, vol. 239, pp. 289–294, 2009.