1 |
L. Friedel, Improved Friction Pressure Drop Correlations for Horizontal and Vertical Two-phase Pipe Flow, European Two-Phase Flow Group Meet, Ispra, Italy, 1979.
|
2 |
Y. Taitel, A.E. Dukler, Flow Regime Transition for Vertical Upward Gas-Liquid Flow, in: AICHE 70th Annual Meeting, 1979. New York).
|
3 |
J.R.S. Thom, Prediction of pressure drop during forced circulation boiling of water, Int. J. Heat Mass Transf. 7 (1964) 709-724.
DOI
|
4 |
D. Chisholm, Two-phase flow in bends, Int. J. Multiph. Flow 6 (4) (1980) 363-367.
DOI
|
5 |
K.C. Jain, Self-sustained Hydrodynamic Oscillations in a Natural-Circulation Two-Phase-Flow Boiling Loop, Argonne National Laboratory Report, 1965. ANL-7073.
|
6 |
B. Schoen, P. Weber, Nitrogen in a steam generator of a PWR under SBLOCA conditions: experimental investigations in the PKL test facility and comparison with analytical studies, Exp. Therm. Fluid Sci. 15 (1997) 238-252.
DOI
|
7 |
Y.J. Chung, H.C. Kim, M.H. Chang, Post test analysis to natural circulation experiment on the BETHSY facility using the MARS 1.4 code, J. Korean Nucl. Soc. 33 (6) (2001) 638-651.
|
8 |
Y.M. Ferng, C.H. Lee, Numerical simulation of natural circulation experiments conducted at the IIST facility, Nucl. Eng. Des. 148 (1994) 119-128.
DOI
|
9 |
J. Sanders, Stability of single-phase natural circulation with inverted U-tube steam generators, J. Heat Transf. 110 (1988) 735-742.
DOI
|
10 |
J.L. Hao, W.Z. Chen, D. Zhang, Effect of U-tube length on reverse flow in UTSG primary side under natural circulation, Ann. Nucl. Energy 56 (2013) 66-70.
DOI
|
11 |
J.L. Hao, W.Z. Chen, G.J. Hu, X. Chu, D. Zhang, L. Yu, Experimental research on reverse flow critical point among parallel U-tubes in SG, Prog. Nucl. Energy 98 (2017) 59-70.
DOI
|
12 |
J.J. Jeong, M. Hwang, Y.J. Lee, B.D. Chung, Non uniform flow distribution in the steam generator U-tubes of a pressurized water reactor plant during single and two-phase natural circulations, Nucl. Eng. Des. 231 (2004) 303-314.
DOI
|
13 |
X. Chu, W.Z. Chen, J.L. Hao, D. Zhang, Investigation on reverse flow phenomenon in UTSGs under two-phase natural circulation with low steam quality, Ann. Nucl. Energy 119 (2018) 1-6.
DOI
|
14 |
W.Z. Chen, L. Yu, J.L. Hao, Thermal Hydraulics of Nuclear Power Plants, Chinese Atomic Energy Press, Beijing, 2013 (in Chinese).
|
15 |
G.B. Wallis, One-dimensional Two-phase Flow, McGraw Hill Book Co., New York City, 1969.
|
16 |
S.N. Kim, W.H. Jang, The simulation of Semiscale natural circulation test S-NC- 3, S-NC-4 using RELAP 5/Mod 3.1, J. Korean Nucl. Soc. 30 (5) (1998) 424-434.
|
17 |
Z.J. Yang, J.Q. Shan, J.L. Gou, Preliminary assessment of a combined passive system for typical 3-loop PWR CPR1000, Nucl. Eng. Des. 313 (2017) 141-161.
DOI
|
18 |
K. Kawanishi, A. Tsuge, M. Fujiwara, Experimental study on heat removal during cold leg small break LOCAs in PWRs, J. Nucl. Sci. Technol. 28 (6) (1991) 555-569.
DOI
|
19 |
V. Kouhia, V. Riikonen, O.P. Kauppinen, Benchmark exercise on SBLOCA experiment of PWR PACTEL facility, Ann. Nucl. Energy 59 (2013) 149-156.
DOI
|
20 |
F. D'Auria, G.M. Galassi, Flowrate and density oscillations during two-phase natural circulation in PWR typical conditions, Nucl. Eng. Des. 122 (1990) 209-218.
DOI
|
21 |
G.F. De Santi, F. Mayinger, Steam condensation and liquid holdup in steam generator U-tubes during oscillatory natural circulation, Exp. Heat Transf. 6 (1993) 367-387.
DOI
|
22 |
Y. Kukita, H. Nakamura, K. Tasaka, Nonuniform steam generator U-tube flow distribution during natural circulation tests in ROSA-IV large scale test facility, Nucl. Sci. Eng. 99 (1988) 289-298.
DOI
|