참고문헌
- J. Weisman and B. S. Pei, 'Prediction of Critical Heat Flux in Flow Boiling at Low Qualities,' Int. J. Heat Mass Transfer 26, 1463 (1983)
- C. H. Lee and I. Mudawar, 'A Mechanistic Critical Heat Flux Model for Subcooled Flow Boiling Based on Local Bulk Flow Conditions,' Int. J. Multiphase Row 14, 714 (1988) https://doi.org/10.1016/0301-9322(88)90070-5
- G. P. Celata., M. Cumo, A. Mariani, M. Simoncini, and G. Zummo, 'Rationalization of Existing Mechanistic Models for the Prediction of Water Subcooled Row Boiling Critical Heat Flux,' Int. J. Heat Mass Transfer 37, suppl.1, 347 (1994)
- G. P. Celata, M. Cumo, and A. Mariani, 'Assessment of Correlations and Models for the Prediction of CHF in Water Subcooled Flow Boiling,' Int. J. Heat Mass Transfer 37, 237 (1994) https://doi.org/10.1016/0017-9310(94)90096-5
- F. Inasaka and H. Nariai, 'Evaluation of Subcooled Critical Heat Flux Correlations for Tubes with and without Internal Twist Tapes,' Nucl. Eng. Des. 163, 225 (1996) https://doi.org/10.1016/0029-5493(95)01170-6
- Y. M. Kwon and S. H. Chang, 'An Improved Mechanistic Model to Predict Critical Heat Flux in Subcooled and Low Quality Forced Convection Boiling,' J. Korean Nucl. Society 31, 236 (1999)
- Y. M. Kwon and S. H. Chang, 'A Mechanistic Critical Heat Flux Model for Wide Range of Subcooled and Low Quality Flow Boiling,' Nucl. Eng. Des. 188, 27 (1999) https://doi.org/10.1016/S0029-5493(99)00025-4
- P. Saha and N. Zuber, 'Point of Net Vapor Generation and Vapor Void Fraction in Subcooled Boiling,' Proc. 5th Int. Heat Transfer Conf., Tokyo, Japan, Vol. IV, pp.175-179(1974)
- F. W. Staub, 'The Void Fraction in Subcooled Boiling - Prediction of the Initial Point of Net Vapor Generation,' J. Heat Transfer 90, 151 (1968)
- S. Levy, 'Forced Convection Subcooled Boiling - Prediction of Vapor Volumetric Fraction,' Int. J. Heat Mass Transfer 10, 951 (1967) https://doi.org/10.1016/0017-9310(67)90071-3
- D. R. H. Beattie and P. B. Whalley, 'A Simple Two Phase Frictional Pressure Drop Calculation Method,' Int. J. Multiphase Flow 8, 83 (1982) https://doi.org/10.1016/0301-9322(82)90009-X
- G. E. Dix, 'Vapor Void Fractions for Forced Convection with Subcooled Boiling at Low Row Rates,' NEDO-10491, General Electric Company (1971)
- O. Styrikovitch, E. I. Nevstrueva, and G. M. Dvorina, 'The Effect of Two Phase Flow Pattern on the Nature of Heat Transfer Crisis in Boiling,' Proc. 4th Int. Heat Transfer Conf., Paris-Versailles, Vol. VI, pp. B 6.10 (1970)
- G. P. Celata, 'Critical Heat Flux in Subcooled Flow Boiling,' Proc. of 11th Int. Heat Transfer Conf., Kyongju, Korea, Vol.1, pp.261-277 (1998)
- H. Nariai and F. Inasaka, 'Critical Heat Flux and Flow Characteristics of Subcooled Flow Boiling with Water in Narrow Tubes,' O. C. Jones and I. Michiyoshi (Ed), Dynamics of Two-Phase Flows, CRC Press, pp.689-708 (1992)
- S. Z. Rouhani and E. Axelsson, 'Calculation of Void Volume Fraction in the Subcooled and Quality Boiling Region,' Int. J. Heat Mass Transfer 13, 383 (1970)
- R. W. Bowring, 'Physical Model Based on Bubble Detachment and Calculation of Steam Voidage in the Subcooled Region of a Heated Channel,' Report HPR-10, Inst. For Atomenergi, Halden, Norway (1962)
- R. T. Lahey Jr. and F. J. Moody, 'The Thermal-Hydraulics of a Boiling Water Nuclear Reactor,' American Nuclear Society, 2nd edn., La Grange Park, Illinois. Chapter 5 (1993)
- O. Levenspiel, 'Collapse of Steam Bubbles in Water,' Ind. Eng. Chem. 51 (1959)
- B. Thompson and R. V. Macbeth, 'Boiling Water Heat Transfer in Uniformly Heated Round Tubes: A Compilation of World Data with Accurate Correlations,' AEEW-R-356 (1964)
- K. M. Becker and G. Strand et al., 'Round Tube Burnout Data for Flow of Boiling Water at Pressure between 30 and 200 bar,' Report KTH-NEL-14 (1971)
- A. Zenkevich, 'Analysis and Generalization of Experimental Data on Heat Transfer Crisis Associated with Forced Convection of Cooling Water in Tubes,' AECL-Tr-Misc-304 (1974)
- Y. Chen, R. Zhou, L. Hao, and H. Chen, 'Critical Heat Flux with Subcooled Boiling of Water at Low Pressure,' 8th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Kyoto, Japan, Vol. 2, pp.958-964 (1997)
- R. D. Boyd, 'Subcooled Water Flow Boiling Experiments under Uniform High Heat Flux Conditions,' Fusion Technology 13, 131 (1988)
- R. D. Boyd, 'Sub cooled Water Row Boiling at 1.66 MPa under Uniform High Heat Flux Conditions,' ASME Winter Annual Meeting, HTD Vol.119, pp.91-15 (1989)
- R. D. Boyd, 'Subcooled Water Flow Boiling Transition and the LID Effect on CHF for a Horizontal Uniformly Heated Tube,' Fusion Technology 18, 317 (1990)
- H. Nariai, F. Inasaka, and H. Kinoshita, 'Critical Heat Rux of Subcooled Row Boiling with and without Internal Twisted Tape under Circumferentially Non-uniform Heating Condition,' Proc. German-Japanese Sympo. On Multiphase Flow, pp.191-205 (1994)
- S. Y. Ahmad, 'Axial Distribution of Bulk Temperature and Void Fraction in a Heated Channel with Inlet Subcooling,' Trans. ASME, J. Heat Transfer 92, 595 (1970)
- A. P. Ornatskii and L. S. Vinyarskii, 'Heat Transfer Crisis in a Forced Flow of Underheated Water in Small-bore Tubes,' High Temperature 3, 400 (1965)
- F. Inasaka and H. Nariai, 'Critical Heat Flux of Subcooled Flow Boiling for Water in Uniformly Heated Straight Tubes,' Fusion. Eng. Des. 19, 329 (1992) https://doi.org/10.1016/0920-3796(92)90007-Q
- C. L. Vandervort, A. E. Bergles, and M. K. Jensen, 'An Experimental Study of Critical Heat Rux in Very High Heat Flux Subcooled Boiling,' Int. J. Heat Mass Transfer 37, 161 (1994) https://doi.org/10.1016/0017-9310(94)90019-1
- G. P. Celata, M. Cumo, and A. Mariani, 'Burnout in Highly Subcooled Water Flow Boiling in Small Diameter Tubes,' Int. J. Heat Mass Transfer 36, 1269 (1993) https://doi.org/10.1016/S0017-9310(05)80096-1