1 |
J. Kubota and T. Tsuchiya, “Hydrodynamic Stability Tests and Analytical Model Development for Once-Through Sodium Heated Steam Generator,” Boiler Dynamic and Control in Nuclear Power Stations, pp. 105-115, (1979)
|
2 |
H. O. Kang et al., Analysis of Once-Through Steam Generator Instability, KAERI Report, KAERI/TR-1068, (1998)
|
3 |
M. Kozeki, H. Nariai, T. Furukawa and K. Kurosu, “A Study of Helically-Coiled Tube Once-Through Steam Generator,” Bulletin of the JSME, Vol.13, pp. 1485-1494, (1970)
DOI
|
4 |
H. Ito, "Friction Factors for Turbulent Flow in Curved Pipes," Trans. ASME J. Basic Eng. Vol. 81, pp. 123-134, (1959)
|
5 |
T. Tsuchiya, J. Kubota, T. Takeuchi and T. Takemura, “Hydrodynamic Stability Tests for LMFBR Sodium Heated Steam Generators,” Proceedings of Japan-US Seminar on Two-Phase Flow Dynamics, pp. 399-414, (1979)
|
6 |
S. Kakac, and H. T. Liu, “Two-Phase Flow Dynamic Instabilities in Boiling System,” Multiphase Flow and Heat Transfer, pp.403-444, (1991)
|
7 |
S. Kalish, and O. E. Dwyer, “Heat Transfer to NaK Flow through Unbaffled Rod Bundle,” Int. J. Heat and Mass Transfer, Vol.10, pp. 1533-1558, (1967)
DOI
ScienceOn
|
8 |
Y. Mori, and W. Nakayama, “Study on Forced Convective Heat Transfer in Curved Pipes,” Int. J. Heat and Mass Transfer, Vol.10, pp.37-59, (1967)
DOI
ScienceOn
|
9 |
V. E. Schrock and L. F. Grossman, Forced Convection Boiling Studies, The University of California Berkeley, Report no.73308-UCX-2182, (1959)
|
10 |
H. C. Unal, “Correlations for the Determination of the Inception Conditions of Density-Wave Oscillations for Forced and Natural Circulation Steam Generator Tubes, Trans. ASME J. Heat Transfer, Vol. 102, pp. 14-19, (1980)
DOI
|
11 |
H. Nariai , “Friction Pressure Drop and Heat Transfer Coefficient of Two-Phase Flow in the Helically Coiled Tube Once-Through Steam Generator for Integrated Type Marine Water Reactor, J. Nuc. Sci. Tec. Vol.19(11), pp. 936~947, 1982
DOI
ScienceOn
|
12 |
J. A. Boure, A. E. Bergles and L. S. Tong, “Review of Two-Phase Flow Instability,” Nuclear Engineering and Design, Vol.25, pp. 165-192, (1973)
DOI
ScienceOn
|
13 |
F. Manabe, T. Kosugi, T. Tsuchiya and J. Endo, “Experimental Studies of Heat Transfer Performance with the NO.2 50MW Steam Generator in Japan,” The Topical Meeting on R&D Fabrication and Operating Experience on Steam Generators for LMFBR's, (1981)
|
14 |
R. P. Waszink, and L. E. Efferding, “Hydrodynamic Stability and Thermal Performance Test of a 1-MWt Sodium Heated Once-Through Steam Generator Model,” ASME paper 73- PWR-16 (1973)
|
15 |
H. K. Kang, H. Y. Kim, J. H. Yoon, J. P. Kim and D. J. Lee, “Development of Simple Analytical Model for Helical Once Through Steam Generator Instability,' Ninth International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-9), San Francisco, California, October 3-8, (1999).
|
16 |
H. C. Unal, M. L. G. van Gasselt, and P. W. P. H. Ludwig, "Dynamic Instabilities in Tubes of a Large Capacity, Straight-Tube, Once-Through Sodium Heated Steam Generator," Int. J. Heat Mass Transfer, Vol. 20, pp.1389-1398, (1977)
DOI
ScienceOn
|
17 |
A. Sano, A. Kanamori, T. Tsuchiya and H. Yamashita, “1- MWt Steam Generator Operating Experience,” ASMEpaper 73-HT-53, (1973)
|
18 |
H. C. Unal, “Density-Wave Oscillations in Sodium Heated Once-Through Steam Generator Tubes,” Trans. ASME J. Heat Transfer, Vol. 103, pp. 485-491
DOI
|